National Library of Energy BETA

Sample records for qualification final

  1. AGC-2 Irradiation Data Qualification Final Report

    SciTech Connect (OSTI)

    Laurence C. Hull

    2012-07-01

    The Graphite Technology Development Program will run a series of six experiments to quantify the effects of irradiation on nuclear grade graphite. The second Advanced Graphite Creep (AGC) experiment (AGC-2) began with Advanced Test Reactor (ATR) Cycle 149A on April 12, 2011, and ended with ATR Cycle 151B on May 5, 2012. The purpose of this report is to qualify AGC-2 irradiation monitoring data following INL Management and Control Procedure 2691, Data Qualification. Data that are Qualified meet the requirements for data collection and use as described in the experiment planning and quality assurance documents. Data that do not meet the requirements are Failed. Some data may not quite meet the requirements, but may still provide some useable information. These data are labeled as Trend. No Trend data were identified for the AGC-2 experiment. All thermocouples functioned throughout the AGC-2 experiment. There was one instance where spurious signals or instrument power interruption resulted in a recorded temperature value being well outside physical reality. This value was identified and labeled as Failed data. All other temperature data are Qualified. All helium and argon gas flow data are within expected ranges. Total gas flow was approximately 50 sccm through the capsule. Helium gas flow was briefly increased to 100 sccm during reactor shutdown. All gas flow data are Qualified. At the start of the experiment, moisture in the outflow gas line increased to 200 ppmv then declined to less than 10 ppmv over a period of 5 days. This increase in moisture coincides with the initial heating of the experiment and drying of the system. Moisture slightly exceeded 10 ppmv three other times during the experiment. While these moisture values exceed the 10 ppmv threshold value, the reported measurements are considered accurate and to reflect moisture conditions in the capsule. All moisture data are Qualified. Graphite creep specimens are subjected to one of three loads, 393 lbf, 491 lbf, or 589 lbf. Loads were consistently within 5% of the specified values throughout the experiment. Stack displacement increased consistently throughout the experiment with total displacement ranging from 1 to 1.5 inches. No anomalous values were identified. During reactor outages, a set of pneumatic rams are used to raise the stacks of graphite creep specimens to ensure the specimens have not become stuck within the test train. This stack raising was performed after all cycles when the capsule was in the reactor. All stacks were raised successfully after each cycle. The load and displacement data are Qualified

  2. AGC-3 IRRADIATION DATA QUALIFICATION FINAL REPORT

    SciTech Connect (OSTI)

    Hull, Laurence

    2014-08-01

    All thermocouples functioned throughout the AGC-3 experiment. There was one interval between Dec 18, 2012 and Dec 20, 2012 where 10 NULL values were reported for various thermocouples. These NULL values were deleted from the database. All temperature data are Qualified. During Oct and Nov 2013, 135,849 helium and argon gas flow values were below 0. These negative gas flow values are not correct and are Failed. The remaining argon, helium, and total gas flow data are within expected ranges and are Qualified. Total gas flow was approximately 50 sccm through the capsule. Helium gas flow was briefly increased to 100 sccm during reactor shutdowns. At the start of the experiment, moisture in the outflow gas line was stuck at a constant value of 335.6174 ppmv for the first cycle. When the capsule was reinstalled in the reactor for Cycle 154B, a new moisture filter was installed. Moisture data from Cycle 152B are Failed. All moisture data from the final three cycles are Qualified. Graphite creep specimens were subjected to one of two loads, 393 lbf or 589 lbf. The experiment plan included three loads, but problems with gas leaks in the rams applying the load to the stacks resulted in lower loads being applied to some of the stacks. While the loads applied are not the loads in the plan, the loads were consistently applied throughout the experiment. Therefore the reported loads are accurate and can be used in analysis of graphite creep. Loads were consistently within 5% of the specified values throughout the experiment. Stack displacement increased consistently throughout the experiment with total displacement ranging from 1 to 1.25 inches. No anomalous values were identified. During reactor outages, a set of pneumatic rams was used to raise the stacks of graphite creep specimens to ensure the specimens had not become stuck within the test train. This stack raising was performed three times; all stacks were raised successfully each time. The load and displacement data are Qualified.

  3. AGC-3 Experiment Irradiation Monitoring Data Qualification Final Report

    SciTech Connect (OSTI)

    Laurence Hull

    2014-10-01

    The Graphite Technology Development Program will run a series of six experiments to quantify the effects of irradiation on nuclear grade graphite. The third experiment, Advanced Graphite Creep 3 (AGC 3), began with Advanced Test Reactor (ATR) Cycle 152B on November 27, 2012, and ended with ATR Cycle 155B on April 23, 2014. This report documents qualification of AGC 3 experiment irradiation monitoring data for use by the Very High Temperature Reactor (VHTR) Technology Development Office (TDO) Program for research and development activities required to design and license the first VHTR nuclear plant. Qualified data meet the requirements for data collection and use as described in the experiment planning and quality assurance documents. Failed data do not meet the requirements. Trend data may not meet the requirements, but may still provide some useable information. All thermocouples (TCs) functioned throughout the AGC 3 experiment. There was one interval between December 18, 2012, and December 20, 2012, where 10 NULL values were reported for various TCs. These NULL values were deleted from the Nuclear Data Management and Analysis System database. All temperature data are Qualified for use by the VHTR TDO Program. Argon, helium, and total gas flow data were within expected ranges and are Qualified for use by the VHTR TDO Program. Total gas flow was approximately 50 sccm through the AGC 3 experiment capsule. Helium gas flow was briefly increased to 100 sccm during ATR shutdowns. At the start of the AGC 3 experiment, moisture in the outflow gas line was stuck at a constant value of 335.6174 ppmv for the first cycle (Cycle 152B). When the AGC 3 experiment capsule was reinstalled in ATR for Cycle 154B, a new moisture filter was installed. Moisture data from Cycle 152B are Failed. All moisture data from the final three cycles (Cycles 154B, 155A, and 155B) are Qualified for use by the VHTR TDO Program.

  4. AGR-2 Final Data Qualification Report for U.S. Capsules - ATR Cycles 147A Through 154B

    SciTech Connect (OSTI)

    Pham, Binh T; Einerson, Jeffrey J

    2014-07-01

    This report provides the data qualification status of AGR-2 fuel irradiation experimental data in four U.S. capsules from all 15 Advanced Test Reactor (ATR) Cycles 147A, 148A, 148B, 149A, 149B, 150A, 150B, 151A, 151B, 152A, 152B, 153A, 153B, 154A, and 154B, as recorded in the Nuclear Data Management and Analysis System (NDMAS). Thus, this report covers data qualification status for the entire AGR-2 irradiation and will replace four previously issued AGR-2 data qualification reports (e.g., INL/EXT-11-22798, INL/EXT-12-26184, INL/EXT-13-29701, and INL/EXT-13-30750). During AGR-2 irradiation, two cycles, 152A and 153A, occurred when the ATR core was briefly at low power, so AGR-2 irradiation data are not used for physics and thermal calculations. Also, two cycles, 150A and 153B, are Power Axial Locator Mechanism (PALM) cycles when the ATR power is higher than during normal cycles. During the first PALM cycle, 150A, the experiment was temporarily moved from the B-12 location to the ATR water canal and during the second PALM cycle, 153B, the experiment was temporarily moved from the B-12 location to the I-24 location to avoid being overheated. During the “Outage” cycle, 153A, seven flow meters were installed downstream from seven Fission Product Monitoring System (FPMS) monitors to measure flows from the monitors and these data are included in the NDMAS database. The AGR-2 data streams addressed in this report include thermocouple (TC) temperatures, sweep gas data (flow rates including new FPM downstream flows, pressure, and moisture content), and FPMS data (release rates and release-to-birth rate ratios [R/Bs]) for each of the four U.S. capsules in the AGR-2 experiment (Capsules 2, 3, 5, and 6). The final data qualification status for these data streams is determined by a Data Review Committee comprised of AGR technical leads, Very High Temperature Reactor (VHTR) Program Quality Assurance (QA), and NDMAS analysts. The Data Review Committee, which convened just before each data qualification report was issued, reviewed the data acquisition process, considered whether the data met the requirements for data collection as specified in QA-approved VHTR data collection plans, examined the results of NDMAS data testing and statistical analyses, and confirmed the qualification status of the data as given in each report. This report performs the following tasks: (1) combine existing qualification status of all AGR-2 data, (2) provide FPMS data qualification update and new release-to-birth ratio (R/B) data calculated using daily calculated birthrates, and (3) revise data qualification status of TC readings for some TCs in Capsule 6 based on their differences relative to calculated temperatures at TC locations. A total of 17,001,695 TC temperature and sweep gas data records were received and processed by NDMAS for four U.S. capsules during AGR-2 irradiation. Of these records, 9,655,474 (56.8% of the total) were determined to be Qualified; 5,792,052 (34.1% of the total) were determined to be Failed; and 1,554,169 (9.1% of the total) were determined to be Trend. For the first nice cycles, from ATR Cycle 147A to 151B, data records are 5- minute or 10-minute averaged values provided on weekly basis in EXCEL spreadsheets. For the last six cycles, ATR Cycle 152A through 154B, data records are instantaneous measurements recorded every minute and provided by .csv text files automatically every 2 hours. Therefore, the number of processed irradiation data was increased substantially from ATR Cycle 152A. For TC temperature data, there were 6,857,675 records and of these data 5,288,249 records (77.1% of the total TC data) were Failed due to TC instrument failures and 418,569 records (6.1% of the total TC data) were Trend due to large differences between TC readings and calculated values. By the end of Cycle 154A, all TCs in the AGR-2 test train failed. The overall percentage of Failed TC records is high, to some extent, because TCs failed toward the end of irradiation when the recording frequency was higher. For sweep gas data, there were 10,1

  5. TOUGH2 Software Qualification

    E-Print Network [OSTI]

    2010-01-01

    lower temperatures. TOUGH2 SOFTWARE QUALIFICATION - FEBRUARY131 TOUGH2 SOFTWARE QUALIFICATION - FEBRUARY 1996 v . LISTmesh generators. TOUGH2 SOFTWARE QUALIFICATION - FEBRUARY

  6. Assessor Training Assessor Qualification &

    E-Print Network [OSTI]

    NVLAP Assessor Training Assessor Qualification & Training Requirements #12;Assessor Training 2009: Qualification & Training Requirements 2 References ·ISO/IEC 17011: Conformity assessment General requirements 2 #12;Assessor Training 2009: Qualification & Training Requirements 3 Assessor Defined ·Lead

  7. LMS Qualification and Flight Acceptance T /V Test Summary

    E-Print Network [OSTI]

    Rathbun, Julie A.

    LMS Qualification and Flight Acceptance T /V Test Summary and Thermal Design Final Report NO. ATMIIIIDe yablinaDhllalan LMS Qualification and Flight Acceptance T/V Test Summary and Thermal Design Final Report PAGI DATI SUMMARY The LMS maintains thermal control. within the -10 to +125°F operating temperature

  8. Firearms Qualification Courses Manual

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2002-01-17

    Provides detailed requirements for qualification with various firearms. Errata Sheet 5-29-02. Cancels DOE M 473.2-1.

  9. Qualification of Alternative Fuels

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Qualification of Alternative Fuels May 8, 2012 Pyrolysis Oil Workshop Thomas Butcher Sustainable Energy Technologies Department Applications Baseline - Residential and Light...

  10. Firearms Qualification Courses Manual

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1997-08-21

    Defines the required courses of fire for authorized firearms in order to ensure the uniform qualification and requalification of DOE Federal Officers and Security Police Officers by certified Federal and contractor firearms instructors.

  11. GIS Specialist Qualifications

    E-Print Network [OSTI]

    Mazzotti, Frank

    GIS Specialist Qualifications An opportunity to work with a new and growing organization to take on new challenges with other to provide the best solutions for our clients in which GIS and development of data bases associated with GIS base maps, including updates and coordinates the purchase of GIS

  12. Firearms Qualification Courses Manual

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1997-07-08

    Defines the required courses of fire for authorized firearms in order to ensure the uniform qualification and requalification of DOE Federal Officers and Security Police Officers by certified Federal and contractor firearms instructors. DOE N 251.40, dated 5-3-01, extends this directive until 12-31-01. Cancels DOE M 5632.7-1.

  13. ITOUGH2 software qualification

    SciTech Connect (OSTI)

    Finsterle, S.; Pruess, K.; Fraser, P.

    1996-10-01

    The purpose of this report is to provide all software baseline documents necessary for the software qualification of ITOUGH2. ITOUGH2 is a computer program providing inverse modeling capabilities for TOUGH2. TOUGH2 is a numerical simulation code for multi-dimensional coupled fluid and heat flow of multiphase, multicomponent fluid mixtures in porous and fractured media.

  14. LSPE Qualification and Flight Acceptance T /V Test Su.m..mary and Thermal Design

    E-Print Network [OSTI]

    Rathbun, Julie A.

    LSPE Qualification and Flight Acceptance T /V Test Su.m..mary and Thermal Design Final Report NO. ATM 1110 This ATM Summarizes the analytical and test results of the Lunar Seismic Profiling Experiment summarizes the Qualification and Flight Acceptance thermal vacuum testing programs and the third section

  15. Firearms Qualification Courses Manual

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1992-12-01

    The U.S. Department of Energy (DOE) requires all protective force personnel authorized to carry firearms to receive proper firearms training and qualification. The most important part of such training is the proper use of deadly force, which is included in the DOE Basic Security policy officer Program and is available as a separate program through the Safeguards and Security Central Training Academy. Canceled by DOE M 473.2-1 dated 07/08/1997.

  16. RERTR Fuel Developmemt and Qualification Plan

    SciTech Connect (OSTI)

    Dan Wachs

    2007-01-01

    In late 2003 it became evident that U-Mo aluminum fuels under development exhibited significant fuel performance problems under the irradiation conditions required for conversion of most high-powered research reactors. Solutions to the fuel performance issue have been proposed and show promise in early testing. Based on these results, a Reduced Enrichment Research and Test Reactor (RERTR) program strategy has been mapped to allow generic fuel qualification to occur prior to the end of FY10 and reactor conversion to occur prior to the end of FY14. This strategy utilizes a diversity of technologies, test conditions, and test types. Scoping studies using miniature fuel plates will be completed in the time frame of 2006-2008. Irradiation of larger specimens will occur in the Advanced Test Reactor (ATR) in the United States, the Belgian Reactor-2 (BR2) reactor in Belgium, and in the OSIRIS reactor in France in 2006-2009. These scoping irradiation tests provide a large amount of data on the performance of advanced fuel types under irradiation and allow the down selection of technology for larger scale testing during the final stages of fuel qualification. In conjunction with irradiation testing, fabrication processes must be developed and made available to commercial fabricators. The commercial fabrication infrastructure must also be upgraded to ensure a reliable low enriched uranium (LEU) fuel supply. Final qualification of fuels will occur in two phases. Phase I will obtain generic approval for use of dispersion fuels with density less than 8.5 g-U/cm3. In order to obtain this approval, a larger scale demonstration of fuel performance and fabrication technology will be necessary. Several Materials Test Reactor (MTR) plate-type fuel assemblies will be irradiated in both the High Flux Reactor (HFR) and the ATR (other options include the BR2 and Russian Research Reactor, Dmitrovgrad, Russia [MIR] reactors) in 2008-2009. Following postirradiation examination, a report detailing very-high density fuel behavior will be submitted to the U.S. Nuclear Regulatory Commission (NRC). Assuming acceptable fuel behavior, it is anticipated that NRC will issue a Safety Evaluation Report granting generic approval of the developed fuels based on the qualification report. It is anticipated that Phase I of fuel qualification will be completed prior to the end of FY10. Phase II of the fuel qualification requires development of fuels with density greater than 8.5 g-U/cm3. This fuel is required to convert the remaining few reactors that have been identified for conversion. The second phase of the fuel qualification effort includes both dispersion fuels with fuel particle volume loading on the order of 65 percent, and monolithic fuels. Phase II presents a larger set of technical unknowns and schedule uncertainties than phase I. The final step in the fuel qualification process involves insertion of lead test elements into the converting reactors. Each reactor that plans to convert using the developed high-density fuels will develop a reactor specific conversion plan based upon the reactor safety basis and operating requirements. For some reactors (FRM-II, High-Flux Isotope Reactor [HFIR], and RHF) conversion will be a one-step process. In addition to the U.S. fuel development effort, a Russian fuel development strategy has been developed. Contracts with Russian Federation institutes in support of fuel development for Russian are in place.

  17. ORISE: Training and Qualification Programs

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Training and Qualification Programs As a core part of providing effective communication and training to protect the safety of workers, the Oak Ridge Institute for Science and...

  18. FAQS Gap Analysis Qualification Card – Criticality Safety

    Broader source: Energy.gov [DOE]

    Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard.

  19. FAQS Gap Analysis Qualification Card – Construction Management

    Broader source: Energy.gov [DOE]

    Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard.

  20. FAQS Gap Analysis Qualification Card – Mechanical Systems

    Broader source: Energy.gov [DOE]

    Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard.

  1. FAQS Gap Analysis Qualification Card – Emergency Management

    Broader source: Energy.gov [DOE]

    Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard.

  2. FAQS Gap Analysis Qualification Card – Radiation Protection

    Broader source: Energy.gov [DOE]

    Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard.

  3. FINAL

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would like submitKansasCommunitiesofExtrans - PermeationGovernment |RoboticFIB CORE2 FINAL

  4. FAQS Qualification Card- Aviation Manager

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  5. FAQS Qualification Card – Criticality Safety

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  6. FAQS Qualification Card – Environment Compliance

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  7. FAQS Qualification Card- Construction Management

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  8. FAQS Qualification Card – Emergency Management

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  9. FAQS Qualification Card – Waste Management

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  10. Qualification Status List (QSL Package)

    E-Print Network [OSTI]

    Rathbun, Julie A.

    #12;ALSEP Qualification Status List (QSL Package) Flight 3 Configuration #12;NO. ltiY. NO15 C/S T.imer Bl7 2.3 Passive Seismic Experiment (Bl8-B21) PSE Sensor Assembly Bl8 PSE C. RI!V. NO. Qualification Status List ALSEP Array B Configuration 1. 0 INTRODUCTION ATM 825 PAGI! 1

  11. Technical Qualification Program Self-Assessment Report - Richland...

    Broader source: Energy.gov (indexed) [DOE]

    Technical Qualification Program Self-Assessment Report - Sandia Site Office - 2012 Technical Qualification Program Accreditation Report - Sandia Site Office Technical...

  12. Technical Qualification Program Accreditation Objectives and...

    Energy Savers [EERE]

    competence. TQP Accreditation Objectives and Criteria More Documents & Publications Technical Qualification Program Self-Assessment Report - Sandia Site Office - 2012...

  13. Committee on Educational Policy MAJOR QUALIFICATION POLICY

    E-Print Network [OSTI]

    California at Santa Cruz, University of

    Committee on Educational Policy MAJOR QUALIFICATION POLICY CEP encourages all undergraduate to formalize these guidelines by implementing a policy that restricts qualification to one or more majors. CEP of the major qualifications policy on other undergraduate programs; · discuss the potential effects

  14. Functional Area Qualification Standard Qualification Cards | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum12, 2015ExecutiveFluorescentDanKathyEnergy Qualification Cards Functional

  15. Quality Assurance Functional Area Qualification Standard - DOE...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    nuclear facilities. DOE-STD-1150-2013, Quality Assurance Functional Area Qualification Standard Type: Invoked Technical Standards Status: Current Approved Date: Dec 02, 2013...

  16. Advanced Qualification of Additive Manufacturing Workshop

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Additive Manufacturing Workshop Poster Abstract Submission - deadline July 10, 2015 Advanced Qualification of Additive Manufacturing Materials using in situ sensors, diagnostics...

  17. Advanced Qualification of Additive Manufacturing Workshop

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Workshops Additive Manufacturing Workshop Advanced Qualification of Additive Manufacturing Materials Workshop Our goal is to define opportunities and research gaps within...

  18. Safety Software Quality Assurance Functional Area Qualification...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    72-2011, Safety Software Quality Assurance Functional Area Qualification Standard by Diane Johnson This SSQA FAQS identifies the minimum technical competency requirements for DOE...

  19. Business Case for Technical Qualification Program Accreditation...

    Broader source: Energy.gov (indexed) [DOE]

    Business Case for TQP Accreditation Incentives More Documents & Publications Technical Qualification Program Self-Assessment Report - Los Alamos Site Office - 2007...

  20. Technical Qualification Program Reaccreditation Report - Y-12...

    Energy Savers [EERE]

    Reaccreditation Report - Y-12 Site Office Technical Qualification Program Reaccreditation Report - Y-12 Site Office The accreditation process consists of three distinct activities:...

  1. FAQS Gap Analysis Qualification Card – General Technical Base

    Broader source: Energy.gov [DOE]

    Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard.

  2. 40 MM Grenade Launcher Qualification Requirements at Department...

    Office of Environmental Management (EM)

    40 MM Grenade Launcher Qualification Requirements at Department of Energy Sites, IG-0806 40 MM Grenade Launcher Qualification Requirements at Department of Energy Sites, IG-0806...

  3. FAQS Gap Analysis Qualification Card – Nuclear Explosive Safety Study

    Broader source: Energy.gov [DOE]

    Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard.

  4. FAQS Gap Analysis Qualification Card – Fire Protection Engineering

    Broader source: Energy.gov [DOE]

    Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard.

  5. Technical Qualification Program Self-Assessment Report - Los...

    Office of Environmental Management (EM)

    Los Alamos Site Office - 2013 Technical Qualification Program Self-Assessment Report - Los Alamos Site Office - 2013 This self-assessment of the Technical Qualifications and...

  6. Senior Technical Safety Manager Qualification Program Self-Assessment...

    Office of Environmental Management (EM)

    Senior Technical Safety Manager Qualification Program Self-Assessment - Chief of Nuclear Safety Senior Technical Safety Manager Qualification Program Self-Assessment - Chief of...

  7. AGR-2 Data Qualification Report for ATR Cycle 154B

    SciTech Connect (OSTI)

    Binh Pham; Jeff Einerson

    2014-01-01

    This report provides the data qualification status of Advanced Gas Reactor-2 (AGR-2) fuel irradiation experimental data from Advanced Test Reactor (ATR) Cycle 154B as recorded in the Nuclear Data Management and Analysis System (NDMAS). This is the last cycle of AGR-2 irradiation, as the test train was pulled from the ATR core during the outage portion of ATR Cycle 155A. The AGR-2 data streams addressed in this report include thermocouple (TC) temperatures, sweep gas data (flow rates including new Fission Product Monitoring (FPM) downstream flows from Fission Product Monitoring System (FPMS) detectors, pressure, and moisture content), and FPMS data (release rates and release-to-birth rate ratios [R/Bs]) for each of the six capsules in the AGR-2 experiment. The final data qualification status for these data streams is determined by a Data Review Committee (DRC) comprised of AGR technical leads, Sitewide Quality Assurance (QA), and NDMAS analysts. The Data Review Committee reviewed the data acquisition process, considered whether the data met the requirements for data collection as specified in QA-approved Very High Temperature Reactor (VHTR) data collection plans, examined the results of NDMAS data testing and statistical analyses, and confirmed the qualification status of the data as given in this report.

  8. Certification Date: 05 / 05 / 2015 (Official Stamp/Seal) 1. HOLDER OF THE QUALIFICATION

    E-Print Network [OSTI]

    Oldenburg, Carl von Ossietzky Universität

    Certification Date: 05 / 05 / 2015 (Official Stamp/Seal) 1. HOLDER OF THE QUALIFICATION 1.1 Family the second semester onwards. Working in small groups on professionally oriented problems, students-week internship in a company or in a research facility is required to complete the program. The final thesis

  9. FAQS Qualification Card- Aviation Safety Officer

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  10. FAQS Qualification Card – Fire Protection Engineering

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  11. FAQS Qualification Card- Civil Structural Engineering

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  12. FAQS Qualification Card – Safeguards and Security

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  13. FAQS Qualification Card – Safety Software Quality Assurance

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  14. FAQS Qualification Card – Technical Program Manager

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  15. FAQS Qualification Card – Senior Technical Safety Manager

    Office of Energy Efficiency and Renewable Energy (EERE)

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  16. FAQS Qualification Card – Facility Maintenance Management

    Office of Energy Efficiency and Renewable Energy (EERE)

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  17. FAQS Qualification Card – Nuclear Operations Specialist

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  18. FAQS Qualification Card – Nuclear Explosive Safety Study

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  19. Methods Data Qualification Interim Report

    SciTech Connect (OSTI)

    R. Sam Alessi; Tami Grimmett; Leng Vang; Dave McGrath

    2010-09-01

    The overall goal of the Next Generation Nuclear Plant (NGNP) Data Management and Analysis System (NDMAS) is to maintain data provenance for all NGNP data including the Methods component of NGNP data. Multiple means are available to access data stored in NDMAS. A web portal environment allows users to access data, view the results of qualification tests and view graphs and charts of various attributes of the data. NDMAS also has methods for the management of the data output from VHTR simulation models and data generated from experiments designed to verify and validate the simulation codes. These simulation models represent the outcome of mathematical representation of VHTR components and systems. The methods data management approaches described herein will handle data that arise from experiment, simulation, and external sources for the main purpose of facilitating parameter estimation and model verification and validation (V&V). A model integration environment entitled ModelCenter is used to automate the storing of data from simulation model runs to the NDMAS repository. This approach does not adversely change the why computational scientists conduct their work. The method is to be used mainly to store the results of model runs that need to be preserved for auditing purposes or for display to the NDMAS web portal. This interim report demonstrates the currently development of NDMAS for Methods data and discusses data and its qualification that is currently part of NDMAS.

  20. Technical Qualification Program Self-Assessment Report - Los...

    Office of Environmental Management (EM)

    Field Office - FY14 Technical Qualification Program Self-Assessment Report - Los Alamos Field Office - FY14 The FY14 self-assessment of the Technical Qualifications Program and...

  1. New geothermal site identification and qualification. Final report

    SciTech Connect (OSTI)

    Not Available

    2004-04-01

    This study identifies remaining undeveloped geothermal resources in California and western Nevada, and it estimates the development costs of each. It has relied on public-domain information and such additional data as geothermal developers have chosen to make available. Reserve estimation has been performed by volumetric analysis with a probabilistic approach to uncertain input parameters. Incremental geothermal reserves in the California/Nevada study area have a minimum value of 2,800 grosss MW and a most-likely value of 4,300 gross MW. For the state of California alone, these values are 2,000 and 3,000 gross MW, respectively. These estimates may be conservative to the extent that they do not take into account resources about which little or no public-domain information is available. The average capital cost of incremental generation capacity is estimated to average $3,100/kW for the California/Nevada study area, and $2,950/kW for the state of California alone. These cost estimates include exploration, confirmation drilling, development drilling, plant construction, and transmission-line costs. For the purposes of this study, a capital cost of $2,400/kW is considered competitive with other renewable resources. The amount of incremental geothermal capacity available at or below $2,400/kW is about 1,700 gross MW for the California/Nevada study area, and the same amount (within 50-MW rounding) for the state of California alone. The capital cost estimates are only approximate, because each developer would bring its own experience, bias, and opportunities to the development process. Nonetheless, the overall costs per project estimated in this study are believed to be reasonable.

  2. Industrial engineering study of tank farm access qualifications and validations

    SciTech Connect (OSTI)

    Sterling, S.G., Westinghouse Hanford

    1996-07-01

    Engineering study of alternatives to reduce costs of validation worker`s qualification prior to Tank Farm area access.

  3. SEISMIC ENGINEERING RESEARCH INFRASTRUCTURES FOR EUROPEAN SYNERGIES Qualification

    E-Print Network [OSTI]

    SEISMIC ENGINEERING RESEARCH INFRASTRUCTURES FOR EUROPEAN SYNERGIES Qualification of Seismic Research Facilities in Europe Maurizio Zola (P&P LMC - Bergamo) ­ Fabio Taucer (JRC ­ Ispra) #12;SEISMIC The qualification of the RTD facilities Standardization of the qualification of the RTD Facilities #12;SEISMIC

  4. 4~APOLLO 14 LRRR QUALIFICATION STATUS LIST

    E-Print Network [OSTI]

    Rathbun, Julie A.

    READINESS QUALIFICATION RATIONALE DIAGRAM "A" ARTHUR D. LITTLE BENDIX AEROSPACE SYSTEMS DIVISION Reflectors Qualified 1 'U : >LRRR I ~ ~ U1 g:: Experiment! o · ...... 00 0' ~ '--- #12;' A. D. LITTLE Apollo 14 Flight ~~/j~A=~P r epa n~d by:_/'.:.._____._,;;:..-'_

  5. AGR-2 Data Qualification Interim Report

    SciTech Connect (OSTI)

    Michael L. Abbott

    2010-09-01

    Projects for the very high temperature reactor (VHTR) Technology Development Office program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program established the NGNP Data Management and Analysis System (NDMAS) to manage and document VHTR data qualification, for storage of the data in a readily accessible electronic form, and to assist in the analysis and presentation of the data. This document gives the status of NDMAS processing and qualification of data associated with the initial reactor cycle (147A) of the second Advanced Gas Reactor (AGR-2) experiment which began on June 21, 2010. Because it is early in the AGR-2 experiment, data from only two AGR-2 data streams are reported on: Fuel Fabrication and Fuel Irradiation data. As of August 1, 2010, approximately 311,000 irradiation data records have been stored in NDMAS, and qualification tests are in progress. Preliminary information indicates that TC 2 in Capsule 2 failed prior to start of the experiment, and NDMAS testing has thus far identified only two invalid data values from the METSO data collection system Data from the Fission Product Monitoring System (FPMS) are not currently processed until after reactor cycle shutdown and have not yet been received. A description of the ATR operating conditions data associated with the AGR-2 experiment (e.g., power levels) are summarized in the AGR-1 data qualification report (INL/EXT-09-16460). Since ATR data are collected under ATR program data quality requirements (i.e., outside the VHTR program), the NGNP program and NDMAS do not take additional actions to qualify these data other than NDMAS capture testing. Data qualification of graphite characterization data collected under the Graphite Technology Development Project is reported in a separate status report (Hull 2010).

  6. Characterization Of The As-Received Sludge Batch 9 Qualification Sample (Htf-51-15-81)

    SciTech Connect (OSTI)

    Pareizs, J.

    2015-09-30

    Savannah River National Laboratory (SRNL) personnel have been requested to qualify the next sludge batch (Sludge Batch 9 – SB9) for processing at the Defense Waste Processing Facility (DWPF). To accomplish this task, Savannah River Remediation (SRR) has sent SRNL a 3-L slurried sample of Tank 51H (HTF-51-15-81) to be characterized, washed, and then used in a lab-scale demonstration of the DWPF flowsheet (potentially after combining with Tank 40H sludge). This report documents the first steps of the qualification process – characterization of the as-received Tank 51H qualification sample. These results will be used to support a reprojection of SB9 by SRR from which final Tank 51H washing, frit development, and Chemical Processing Cell (CPC) activities will be based.

  7. Equipment qualification research program: program plan

    SciTech Connect (OSTI)

    Dong, R.G.; Smith, P.D.

    1982-06-08

    The Lawrence Livermore National Laboratory (LLNL) under the sponsorship of the US Nuclear Regulatory Commission (NRC) has developed this program plan for research in equipment qualification (EQA). In this report the research program which will be executed in accordance with this plan will be referred to as the Equipment Qualification Research Program (EQRP). Covered are electrical and mechanical equipment under the conditions described in the OBJECTIVE section of this report. The EQRP has two phases; Phase I is primarily to produce early results and to develop information for Phase II. Phase I will last 18 months and consists of six projects. The first project is program management. The second project is responsible for in-depth evaluation and review of EQ issues and EQ processes. The third project is responsible for detailed planning to initiate Phase II. The remaining three projects address specific equipment; i.e., valves, electrical equipment, and a pump.

  8. Request for Qualifications for Sacramento Landfill

    Office of Energy Efficiency and Renewable Energy (EERE)

    This Request for Qualifications (RFQ) solicits experienced companies to design, permit, finance, build, and operate a solar photovoltaic farm (SPV Farm) on the City of Sacramento’s 28th Street Landfill. Respondents to this RFQ must demonstrate experience and capacity to design, permit, finance, build, and operate a SPV Farm that generates electricity that can be sold for electrical use through a power-purchase agreement. Submittals must be prepared and delivered in accordance with the requirements set forth in this document.

  9. High Temperature Materials Interim Data Qualification Report

    SciTech Connect (OSTI)

    Nancy Lybeck

    2010-08-01

    ABSTRACT Projects for the very high temperature reactor (VHTR) Technology Development Office provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program has established the NGNP Data Management and Analysis System (NDMAS) to ensure that VHTR data are qualified for use, stored in a readily accessible electronic form, and analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the High Temperature Materials characterization data stream, the processing of these data within NDMAS, and reports the interim FY2010 qualification status of the data. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category assigned by the data generator. The High Temperature Materials data are being collected under NQA-1 guidelines, and will be qualified data. For NQA-1 qualified data, the qualification activities include: (1) capture testing, to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing to confirm that the data are an accurate representation of the system or object being measured, and (3) documenting that the data were collected under an NQA-1 or equivalent Quality Assurance program. Currently, data from two test series within the High Temperature Materials data stream have been entered into the NDMAS vault: 1. Tensile Tests for Sm (i.e., Allowable Stress) Confirmatory Testing – 1,403,994 records have been inserted into the NDMAS database. Capture testing is in process. 2. Creep-Fatigue Testing to Support Determination of Creep-Fatigue Interaction Diagram – 918,854 records have been processed and inserted into the NDMAS database. Capture testing is in process.

  10. Functional Area Qualification Standards | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum12, 2015ExecutiveFluorescentDanKathyEnergy QualificationStandards Functional

  11. Construction, Qualification, and Low Rate Production Start-up...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Manufacturing Facility with Capacity to Support 100,000 Electric Drive Vehicles Construction, Qualification, and Low Rate Production Start-up of a DC Bus Capacitor High Volume...

  12. Technical Qualification Program Self-Assessment Report - NNSA...

    Office of Environmental Management (EM)

    NNSA Production Office - 2014 Technical Qualification Program Self-Assessment Report - NNSA Production Office - 2014 In preparation for the upcoming Chief for Defense Nuclear...

  13. Technical Qualification Program Self-Assessment Report - Livermore...

    Broader source: Energy.gov (indexed) [DOE]

    nuclear facilities. LFO TQP Self-Assessment, May 2013 More Documents & Publications Technical Qualification Program Self-Assessment Report - NA-SH - 2013 Technical...

  14. Technical Qualification Program Self-Assessment Report - Nevada...

    Office of Environmental Management (EM)

    Nevada Field Office - 2014 Technical Qualification Program Self-Assessment Report - Nevada Field Office - 2014 This self-assessment examined how the Nevada Field Office (NFO)...

  15. Technical Qualification Program Self-Assessment Report - Los...

    Office of Environmental Management (EM)

    07 Technical Qualification Program Self-Assessment Report - Los Alamos Site Office - 2007 The Federal Technical Capability Manual requires periodic self-assessment of the...

  16. Defense Program Equivalencies for Technical Qualification Standard Competencies12/12/1995

    Broader source: Energy.gov [DOE]

    Defense Programs has undertaken an effort to compare the competencies in the GeneralTechnical Base Qualification Standard and the Functional Area Qualification Standards withvarious positions in...

  17. SEISMIC ENGINEERING RESEARCH INFRASTRUCTURES FOR EUROPEAN SYNERGIES 1 SERIES Final Workshop , Ispra, 28-30 May 2013

    E-Print Network [OSTI]

    SEISMIC ENGINEERING RESEARCH INFRASTRUCTURES FOR EUROPEAN SYNERGIES 1 SERIES Final Workshop , Ispra, 28-30 May 2013 SERIES Networking Activities: Distributed database and Qualification of Research Infrastructures Opening remarks Pierre Pegon (JRC) #12;SEISMIC ENGINEERING RESEARCH INFRASTRUCTURES FOR EUROPEAN

  18. FAQS Qualification Card – Safeguards and Security General Technical Base

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  19. Qualification Plus: Performance and Durability Tests Beyond IEC 61215 (Presentation)

    SciTech Connect (OSTI)

    Kurtz, S.; Jordan, J.; Kempe, M.; Miller, D.; Bosco, N.; Silverman, T.; Hacke, P.; Phillips, N.; Earnest, T.; Romero, R.

    2014-03-01

    Qualification Plus is an accelerated test protocol and quality management system that gives higher confidence in field performance of PV modules compared with conventional qualification testing. The test sequences are being developed as consensus standards, but the early publication of these tests enables the community to begin benefiting from them sooner.

  20. Large Bore Powder Gun Qualification (U)

    SciTech Connect (OSTI)

    Rabern, Donald A.; Valdiviez, Robert

    2012-04-02

    A Large Bore Powder Gun (LBPG) is being designed to enable experimentalists to characterize material behavior outside the capabilities of the NNSS JASPER and LANL TA-55 PF-4 guns. The combination of these three guns will create a capability to conduct impact experiments over a wide range of pressures and shock profiles. The Large Bore Powder Gun will be fielded at the Nevada National Security Site (NNSS) U1a Complex. The Complex is nearly 1000 ft below ground with dedicated drifts for testing, instrumentation, and post-shot entombment. To ensure the reliability, safety, and performance of the LBPG, a qualification plan has been established and documented here. Requirements for the LBPG have been established and documented in WE-14-TR-0065 U A, Large Bore Powder Gun Customer Requirements. The document includes the requirements for the physics experiments, the gun and confinement systems, and operations at NNSS. A detailed description of the requirements is established in that document and is referred to and quoted throughout this document. Two Gun and Confinement Systems will be fielded. The Prototype Gun will be used primarily to characterize the gun and confinement performance and be the primary platform for qualification actions. This gun will also be used to investigate and qualify target and diagnostic modifications through the life of the program (U1a.104 Drift). An identical gun, the Physics Gun, will be fielded for confirmatory and Pu experiments (U1a.102D Drift). Both guns will be qualified for operation. The Gun and Confinement System design will be qualified through analysis, inspection, and testing using the Prototype Gun for the majority of process. The Physics Gun will be qualified through inspection and a limited number of qualification tests to ensure performance and behavior equivalent to the Prototype gun. Figure 1.1 shows the partial configuration of U1a and the locations of the Prototype and Physics Gun/Confinement Systems.

  1. Waste Form Qualification Compliance Strategy for Bulk Vitrification

    SciTech Connect (OSTI)

    Bagaasen, Larry M.; Westsik, Joseph H.; Brouns, Thomas M.

    2005-01-03

    The Bulk Vitrification System is being pursued to assist in immobilizing the low-activity tank waste from the 53 million gallons of radioactive waste in the 177 underground storage tanks on the Hanford Site. To demonstrate the effectiveness of the bulk vitrification process, a research and development facility known as the Demonstration Bulk Vitrification System (DBVS) is being built to demonstrate the technology. Specific performance requirements for the final packaged bulk vitrification waste form have been identified. In addition to the specific product-performance requirements, performance targets/goals have been identified that are necessary to qualify the waste form but do not lend themselves to specifications that are easily verified through short-term testing. Collectively, these form the product requirements for the DBVS. This waste-form qualification (WFQ) strategy document outlines the general strategies for achieving and demonstrating compliance with the BVS product requirements. The specific objectives of the WFQ activities are discussed, the bulk vitrification process and product control strategy is outlined, and the test strategy to meet the WFQ objectives is described. The DBVS product performance targets/goals and strategies to address those targets/goals are described. The DBVS product-performance requirements are compared to the Waste Treatment and Immobilization Plant immobilized low-activity waste product specifications. The strategies for demonstrating compliance with the bulk vitrification product requirements are presented.

  2. Test of the Qualification Model of UG electronics

    E-Print Network [OSTI]

    Roma "La Sapienza", Universitŕ di

    Test of the Qualification Model of UG electronics for the AMS TRD Gas System Bruno Borgia.1 The UG-crate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 1.2 Test setup . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 1.3 Functionality test sequence . . . . . . . . . . . . . . . . . . . . . . . . 6 2 QM2

  3. Construction, Qualification, and Low Rate Production Start-up...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    of a DC Bus Capacitor High Volume Manufacturing Facility with Capacity to Support 100,000 Electric Drive Vehicles Construction, Qualification, and Low Rate Production Start-up of a...

  4. Technical Qualification Program Self-Assessment Report - Los...

    Office of Environmental Management (EM)

    11 Technical Qualification Program Self-Assessment Report - Los Alamos Site Office - 2011 The purpose of the FTCP TQP self-assessment team evaluation was to conduct a thorough...

  5. SRNL PHASE 1 ASSESSMENT OF THE WTP WASTE QUALIFICATION PROGRAM

    SciTech Connect (OSTI)

    Peeler, D.; Hansen, E.; Herman, C.; Marra, S.; Wilmarth, B.

    2012-03-06

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) Project is currently transitioning its emphasis from an engineering design and construction phase toward facility completion, start-up and commissioning. With this transition, the WTP Project has initiated more detailed assessments of the requirements that must be met during the actual processing of the Hanford Site tank waste. One particular area of interest is the waste qualification program. In general, the waste qualification program involves testing and analysis to demonstrate compliance with waste acceptance criteria, determine waste processability, and demonstrate laboratory-scale unit operations to support WTP operations. The testing and analysis are driven by data quality objectives (DQO) requirements necessary for meeting waste acceptance criteria for transfer of high-level wastes from the tank farms to the WTP, and for ensuring waste processability including proper glass formulations during processing within the WTP complex. Given the successful implementation of similar waste qualification efforts at the Savannah River Site (SRS) which were based on critical technical support and guidance from the Savannah River National Laboratory (SRNL), WTP requested subject matter experts (SMEs) from SRNL to support a technology exchange with respect to waste qualification programs in which a critical review of the WTP program could be initiated and lessons learned could be shared. The technology exchange was held on July 18-20, 2011 in Richland, Washington, and was the initial step in a multi-phased approach to support development and implementation of a successful waste qualification program at the WTP. The 3-day workshop was hosted by WTP with representatives from the Tank Operations Contractor (TOC) and SRNL in attendance as well as representatives from the US DOE Office of River Protection (ORP) and the Defense Nuclear Facility Safety Board (DNFSB) Site Representative office. The purpose of the workshop was to share lessons learned and provide a technology exchange to support development of a technically defensible waste qualification program. The objective of this report is to provide a review, from SRNL's perspective, of the WTP waste qualification program as presented during the workshop. In addition to SRNL's perspective on the general approach to the waste qualification program, more detailed insight into the specific unit operations presented by WTP during the workshop is provided. This report also provides a general overview of the SRS qualification program which serves as a basis for a comparison between the two programs. Recommendations regarding specific steps are made based on the review and SRNL's lessons learned from qualification of SRS low-activity waste (LAW) and high-level waste (HLW) to support maturation of the waste qualification program leading to WTP implementation.

  6. Secondary Waste Cast Stone Waste Form Qualification Testing Plan

    SciTech Connect (OSTI)

    Westsik, Joseph H.; Serne, R. Jeffrey

    2012-09-26

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is being constructed to treat the 56 million gallons of radioactive waste stored in 177 underground tanks at the Hanford Site. The WTP includes a pretreatment facility to separate the wastes into high-level waste (HLW) and low-activity waste (LAW) fractions for vitrification and disposal. The LAW will be converted to glass for final disposal at the Integrated Disposal Facility (IDF). Cast Stone – a cementitious waste form, has been selected for solidification of this secondary waste stream after treatment in the ETF. The secondary-waste Cast Stone waste form must be acceptable for disposal in the IDF. This secondary waste Cast Stone waste form qualification testing plan outlines the testing of the waste form and immobilization process to demonstrate that the Cast Stone waste form can comply with the disposal requirements. Specifications for the secondary-waste Cast Stone waste form have not been established. For this testing plan, Cast Stone specifications are derived from specifications for the immobilized LAW glass in the WTP contract, the waste acceptance criteria for the IDF, and the waste acceptance criteria in the IDF Permit issued by the State of Washington. This testing plan outlines the testing needed to demonstrate that the waste form can comply with these waste form specifications and acceptance criteria. The testing program must also demonstrate that the immobilization process can be controlled to consistently provide an acceptable waste form product. This testing plan also outlines the testing needed to provide the technical basis for understanding the long-term performance of the waste form in the disposal environment. These waste form performance data are needed to support performance assessment analyses of the long-term environmental impact of the secondary-waste Cast Stone waste form in the IDF

  7. LL/ILW: Post-Qualification of Old Waste through Non-Destructive Extraction of Barrels from Cement Shields - 13535

    SciTech Connect (OSTI)

    Oehmigen, Steffen; Ambos, Frank

    2013-07-01

    Currently there is a large number of radioactive waste drums entombed in cement shields at German nuclear power plants. These concrete containers used in the past for the waste are not approved for the final repository. Compliance with current acceptance criteria of the final repository has to be proven by qualification measures on the waste. To meet these criteria, a new declaration and new packing is necessary. A simple non-destructive extraction of about 2000 drums from their concrete shields is not possible. So different methods were tested to find a way of non-destructive extraction of old waste drums from cement shields and therefore reduce the final repository volume and final repository costs by using a container accepted and approved for Konrad. The main objective was to build a mobile system to offer this service to nuclear plant stations. (authors)

  8. Sludge Washing And Demonstration Of The DWPF Flowsheet In The SRNL Shielded Cells For Sludge Batch 8 Qualification

    SciTech Connect (OSTI)

    Pareizs, J. M.; Crawford, C. L.

    2013-04-26

    The current Waste Solidification Engineering (WSE) practice is to prepare sludge batches in Tank 51 by transferring sludge from other tanks to Tank 51. Tank 51 sludge is washed and transferred to Tank 40, the current Defense Waste Processing Facility (DWPF) feed tank. Prior to transfer of Tank 51 to Tank 40, the Savannah River National Laboratory (SRNL) typically simulates the Tank Farm and DWPF processes using a Tank 51 sample (referred to as the qualification sample). WSE requested the SRNL to perform characterization on a Sludge Batch 8 (SB8) sample and demonstrate the DWPF flowsheet in the SRNL shielded cells for SB8 as the final qualification process required prior to SB8 transfer from Tank 51 to Tank 40. A 3-L sample from Tank 51 (the SB8 qualification sample; Tank Farm sample HTF-51-12-80) was received by SRNL on September 20, 2012. The as-received sample was characterized prior to being washed. The washed material was further characterized and used as the material for the DWPF process simulation including a Sludge Receipt and Adjustment Tank (SRAT) cycle, a Slurry Mix Evaporator (SME) cycle, and glass fabrication and chemical durability measurements.

  9. Overview of Progress on the IEC Tracker Design Qualification Standard (Presentation)

    SciTech Connect (OSTI)

    Muller, M.

    2012-03-01

    An update is given on the IEC WG7's progress to write and publish a tracker design qualification standard.

  10. SLUDGE BATCH 7B QUALIFICATION ACTIVITIES WITH SRS TANK FARM SLUDGE

    SciTech Connect (OSTI)

    Pareizs, J.; Click, D.; Lambert, D.; Reboul, S.

    2011-11-16

    Waste Solidification Engineering (WSE) has requested that characterization and a radioactive demonstration of the next batch of sludge slurry - Sludge Batch 7b (SB7b) - be completed in the Shielded Cells Facility of the Savannah River National Laboratory (SRNL) via a Technical Task Request (TTR). This characterization and demonstration, or sludge batch qualification process, is required prior to transfer of the sludge from Tank 51 to the Defense Waste Processing Facility (DWPF) feed tank (Tank 40). The current WSE practice is to prepare sludge batches in Tank 51 by transferring sludge from other tanks. Discharges of nuclear materials from H Canyon are often added to Tank 51 during sludge batch preparation. The sludge is washed and transferred to Tank 40, the current DWPF feed tank. Prior to transfer of Tank 51 to Tank 40, SRNL typically simulates the Tank Farm and DWPF processes with a Tank 51 sample (referred to as the qualification sample). With the tight schedule constraints for SB7b and the potential need for caustic addition to allow for an acceptable glass processing window, the qualification for SB7b was approached differently than past batches. For SB7b, SRNL prepared a Tank 51 and a Tank 40 sample for qualification. SRNL did not receive the qualification sample from Tank 51 nor did it simulate all of the Tank Farm washing and decanting operations. Instead, SRNL prepared a Tank 51 SB7b sample from samples of Tank 7 and Tank 51, along with a wash solution to adjust the supernatant composition to the final SB7b Tank 51 Tank Farm projections. SRNL then prepared a sample to represent SB7b in Tank 40 by combining portions of the SRNL-prepared Tank 51 SB7b sample and a Tank 40 Sludge Batch 7a (SB7a) sample. The blended sample was 71% Tank 40 (SB7a) and 29% Tank 7/Tank 51 on an insoluble solids basis. This sample is referred to as the SB7b Qualification Sample. The blend represented the highest projected Tank 40 heel (as of May 25, 2011), and thus, the highest projected noble metals content for SB7b. Characterization was performed on the Tank 51 SB7b samples and SRNL performed DWPF simulations using the Tank 40 SB7b material. This report documents: (1) The preparation and characterization of the Tank 51 SB7b and Tank 40 SB7b samples. (2) The performance of a DWPF Chemical Process Cell (CPC) simulation using the SB7b Tank 40 sample. The simulation included a Sludge Receipt and Adjustment Tank (SRAT) cycle, where acid was added to the sludge to destroy nitrite and reduce mercury, and a Slurry Mix Evaporator (SME) cycle, where glass frit was added to the sludge in preparation for vitrification. The SME cycle also included replication of five canister decontamination additions and concentrations. Processing parameters were based on work with a nonradioactive simulant. (3) Vitrification of a portion of the SME product and characterization and durability testing (as measured by the Product Consistency Test (PCT)) of the resulting glass. (4) Rheology measurements of the SRAT receipt, SRAT product, and SME product. This program was controlled by a Task Technical and Quality Assurance Plan (TTQAP), and analyses were guided by an Analytical Study Plan. This work is Technical Baseline Research and Development (R&D) for the DWPF. It should be noted that much of the data in this document has been published in interoffice memoranda. The intent of this technical report is bring all of the SB7b related data together in a single permanent record and to discuss the overall aspects of SB7b processing.

  11. Personnel Selection, Training, Qualification, and Certification...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    dated 7-29-13. o426.2Final4-21-10.pdf -- PDF Document, 221 KB Writer: Sam Rosenbloom Subjects: Safety ID: DOE O 426.2 Type: Order OPI: HS - Office of Health, Safety and Security...

  12. COS G130M FUV Grating Calibration And Qualification Plan

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS G130M FUV Grating Calibration And Qualification Plan Date: October 11, 1999 Document Number: COS-01-0002 Revision: Initial Release Contract No.: NAS5-98043 CDRL No. AV-02 Prepared By: S. Osterman, COS Optical Scientist, CU/CASA Date Reviewed By: E. Wilkinson, COS Instrument Scientist, CU/CASA Date

  13. COS G160M FUV Grating Calibration and Qualification Plan

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS G160M FUV Grating Calibration and Qualification Plan Date: January 4, 2001 Document Number: COS-01-0005 Revision: Initial Release Contract No.: NAS5-98043 CDRL No. Prepared By: S. Osterman, COS Optical Scientist, CU/CASA Date Reviewed By: E. Wilkinson, COS Instrument Scientist, CU/CASA Date Approved

  14. COS G140L FUV Grating Calibration and Qualification Plan

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS G140L FUV Grating Calibration and Qualification Plan Date: January 4, 2001 Document Number: COS-01-0004 Revision: Initial Release Contract No.: NAS5-98043 CDRL No. Prepared By: S. Osterman, COS Optical Scientist, CU/CASA Date Reviewed By: E. Wilkinson, COS Instrument Scientist, CU/CASA Date Approved

  15. Personnel Selection, Qualification, and Training Requirements for DOE Nuclear Facilities

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2001-07-12

    To establish selection, qualification, and training requirements for management and operating (M&O) contractor personnel involved in the operation, maintenance, and technical support of Department of Energy and National Nuclear Security Administration Category A and B reactors and non-reactor nuclear facilities. Canceled by DOE O 426.2

  16. Idaho National Engineering and Environmental Laboratory Licensing Qualification Issues

    E-Print Network [OSTI]

    /shutdown is not like PWR criticality control/reactor shutdown system, neither in required timing nor consequences · Approach to Regulatory Approval · Nuclear Design Codes · Summary #12;Idaho National Engineering endeavors · In nuclear systems, the activities that comprise the qualification have two parts: ­ Design

  17. Code qualification of structural materials for AFCI advanced recycling reactors.

    SciTech Connect (OSTI)

    Natesan, K.; Li, M.; Majumdar, S.; Nanstad, R.K.; Sham, T.-L.

    2012-05-31

    This report summarizes the further findings from the assessments of current status and future needs in code qualification and licensing of reference structural materials and new advanced alloys for advanced recycling reactors (ARRs) in support of Advanced Fuel Cycle Initiative (AFCI). The work is a combined effort between Argonne National Laboratory (ANL) and Oak Ridge National Laboratory (ORNL) with ANL as the technical lead, as part of Advanced Structural Materials Program for AFCI Reactor Campaign. The report is the second deliverable in FY08 (M505011401) under the work package 'Advanced Materials Code Qualification'. The overall objective of the Advanced Materials Code Qualification project is to evaluate key requirements for the ASME Code qualification and the Nuclear Regulatory Commission (NRC) approval of structural materials in support of the design and licensing of the ARR. Advanced materials are a critical element in the development of sodium reactor technologies. Enhanced materials performance not only improves safety margins and provides design flexibility, but also is essential for the economics of future advanced sodium reactors. Code qualification and licensing of advanced materials are prominent needs for developing and implementing advanced sodium reactor technologies. Nuclear structural component design in the U.S. must comply with the ASME Boiler and Pressure Vessel Code Section III (Rules for Construction of Nuclear Facility Components) and the NRC grants the operational license. As the ARR will operate at higher temperatures than the current light water reactors (LWRs), the design of elevated-temperature components must comply with ASME Subsection NH (Class 1 Components in Elevated Temperature Service). However, the NRC has not approved the use of Subsection NH for reactor components, and this puts additional burdens on materials qualification of the ARR. In the past licensing review for the Clinch River Breeder Reactor Project (CRBRP) and the Power Reactor Innovative Small Module (PRISM), the NRC/Advisory Committee on Reactor Safeguards (ACRS) raised numerous safety-related issues regarding elevated-temperature structural integrity criteria. Most of these issues remained unresolved today. These critical licensing reviews provide a basis for the evaluation of underlying technical issues for future advanced sodium-cooled reactors. Major materials performance issues and high temperature design methodology issues pertinent to the ARR are addressed in the report. The report is organized as follows: the ARR reference design concepts proposed by the Argonne National Laboratory and four industrial consortia were reviewed first, followed by a summary of the major code qualification and licensing issues for the ARR structural materials. The available database is presented for the ASME Code-qualified structural alloys (e.g. 304, 316 stainless steels, 2.25Cr-1Mo, and mod.9Cr-1Mo), including physical properties, tensile properties, impact properties and fracture toughness, creep, fatigue, creep-fatigue interaction, microstructural stability during long-term thermal aging, material degradation in sodium environments and effects of neutron irradiation for both base metals and weld metals. An assessment of modified versions of Type 316 SS, i.e. Type 316LN and its Japanese version, 316FR, was conducted to provide a perspective for codification of 316LN or 316FR in Subsection NH. Current status and data availability of four new advanced alloys, i.e. NF616, NF616+TMT, NF709, and HT-UPS, are also addressed to identify the R&D needs for their code qualification for ARR applications. For both conventional and new alloys, issues related to high temperature design methodology are described to address the needs for improvements for the ARR design and licensing. Assessments have shown that there are significant data gaps for the full qualification and licensing of the ARR structural materials. Development and evaluation of structural materials require a variety of experimental facilities that have been seriously degraded

  18. SLUDGE BATCH 7 ACCEPTANCE EVALUATION: RADIONUCLIDE CONCENTRATIONS IN TANK 51 SB7 QUALIFICATION SAMPLE PREPARED AT SRNL

    SciTech Connect (OSTI)

    Pareizs, J.; Hay, M.

    2011-02-22

    Presented in this report are radionuclide concentrations required as part of the program of qualifying Sludge Batch Seven (SB7) for processing in the Defense Waste Processing Facility (DWPF). The SB7 material is currently in Tank 51 being washed and prepared for transfer to Tank 40. The acceptance evaluation needs to be completed prior to the transfer of the material in Tank 51 to Tank 40. The sludge slurry in Tank 40 has already been qualified for DWPF and is currently being processed as SB6. The radionuclide concentrations were measured or estimated in the Tank 51 SB7 Qualification Sample prepared at Savannah River National Laboratory (SRNL). This sample was prepared from the three liter qualification sample of Tank 51 sludge slurry (HTF-51-10-125) received on September 18, 2010. The sample was delivered to SRNL where it was initially characterized in the Shielded Cells. With consultation from the Liquid Waste Organization, the qualification sample was then modified by several washes and decants, which included addition of Pu from H Canyon and sodium nitrite per the Tank Farm corrosion control program. This final slurry now has a composition expected to be similar to that of the slurry in Tank 51 after final preparations have been made for transfer of that slurry to Tank 40. Determining the radionuclide concentrations in this Tank 51 SB7 Qualification Sample is part of the work requested in Technical Task Request (TTR) No. HLW-DWPF-TTR-2010-0031. The radionuclides included in this report are needed for the DWPF Radiological Program Evaluation, the DWPF Waste Acceptance Criteria (TSR/WAC) Evaluation, and the DWPF Solid Waste Characterization Program (TTR Task I.2). Radionuclides required to meet the Waste Acceptance Product Specifications (TTR Task III.2.) will be measured at a later date after the slurry from Tank 51 has been transferred to Tank 40. Then a sample of the as-processed SB7 will be taken and transferred to SRNL for measurement of these radionuclides. The results presented in this report are those necessary for DWPF to assess if the Tank 51 SB7 sample prepared at SRNL meets the requirements for the DWPF Radiological Program Evaluation, the DWPF Waste Acceptance Criteria evaluation, and the DWPF Solid Waste Characterization Program. Concentrations are given for thirty-four radionuclides along with total alpha and beta activity. Values for total gamma and total gamma plus beta activities are also calculated.

  19. Investigation Into the Scrambling Of Array E Qualification Model

    E-Print Network [OSTI]

    Rathbun, Julie A.

    Investigation Into the Scrambling Of Array E Qualification Model PDU Relays at Turn-On NO. ATM-1087 to eliminate this discrepant operation, Prepared by: $,;15. J. Thomas Approved by: D~. Fithian #12;..aapace ~"'ystems Division Section 1.0 2.0 2. 1 2.2 3.0 3. I 3.2 4.0 4.1 4.2 4.3 4.4 s.o Investigation

  20. Nuclear criticality safety engineer qualification program utilizing SAT

    SciTech Connect (OSTI)

    Baltimore, C.J.; Dean, J.C.; Henson, T.L. [Lockheed Martin Utility Services, Inc., Paducah, KY (United States)

    1996-12-31

    As part of the privatization process of the U.S. uranium enrichment plants, the Paducah Gaseous Diffusion Plant (PGDP) and the Portsmouth Gaseous Diffusion Plant (PORTS) have been in transition from U.S. Department of Energy (DOE) regulatory oversight to U.S. Nuclear Regulatory Commission (NRC) oversight since July 1993. One of the focus areas of this transition has been training and qualification of plant personnel who perform tasks important to nuclear safety, such as nuclear criticality safety (NCS) engineers.

  1. High Temperature Materials Interim Data Qualification Report FY 2011

    SciTech Connect (OSTI)

    Nancy Lybeck

    2011-08-01

    Projects for the very high temperature reactor (VHTR) Technology Development Office provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program has established the Next Generation Nuclear Plant (NGNP) Data Management and Analysis System (NDMAS) to ensure that VHTR data are qualified for use, stored in a readily accessible electronic form, and analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the High Temperature Materials characterization data stream, the processing of these data within NDMAS, and reports the interim fiscal year (FY) 2011 qualification status of the data. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category assigned by the data generator. The High Temperature Materials data are being collected under the Nuclear Quality Assurance (NQA)-1 guidelines and will be qualified data. For NQA-1 qualified data, the qualification activities include: (1) capture testing to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing to confirm that the data are an accurate representation of the system or object being measured, and (3) documenting that the data were collected under an NQA-1 or equivalent Quality Assurance program. Currently, data from seven test series within the High Temperature Materials data stream have been entered into the NDMAS vault, including tensile tests, creep tests, and cyclic tests. Of the 5,603,682 records currently in the vault, 4,480,444 have been capture passed, and capture testing is in process for the remaining 1,123,238.

  2. Clark Energy Group ESCO Qualification Sheet | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based Fuels|Programs |Chart ofClark Energy Group ESCO Qualification Sheet Clark

  3. Functional Area Qualification Standard Reference Guides | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum12, 2015ExecutiveFluorescentDanKathyEnergy Qualification Cards

  4. Functional Area Qualification Standards Review Process | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum12, 2015ExecutiveFluorescentDanKathyEnergy Qualification CardsEnergy

  5. Functional Area Qualification Standards Template | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum12, 2015ExecutiveFluorescentDanKathyEnergy Qualification

  6. Protocol, Qualification Standard for the Site Lead Program - May 2011 |

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested PartiesBuildingBudget || Department ofDepartment of Energy Qualification

  7. Technical Qualification Program Self-Assessment Report- Office of River Protection- 2014

    Broader source: Energy.gov [DOE]

    A self-assessment was performed in accordance with TRS-OA-IP-07, Management (Self) Assessment, Rev. 2, where information was retrieved from MGT-QT-PL-01, Technical Qualification Program (TQP) Plan, Rev. 3; MGT-QT-DI-01, Technical Qualification Program: Federal Technical Capability Agent Duties, Rev. 2; technical staff electronic training and qualifications files; and ORP's technical staff hard copy training and qualification files to determine the effectiveness of the implemented program and identify any weaknesses of the existing program at turn-over of responsibilities.

  8. Technical Qualification Program Self-Assessment Report- Pacific Northwest Site Office- 2013

    Broader source: Energy.gov [DOE]

    This self-assessment evaluated how well the Technical Qualification and Federal Capability Programs were implemented at the Pacific Northwest Site Office (PNSO).

  9. Final Agenda

    Office of Environmental Management (EM)

    Finally, participants will have a chance to see Argonne's Advanced Photon Source and Blue GeneP supercomputer - cutting-edge facilities that support the lab's ongoing mission...

  10. Final Report

    SciTech Connect (OSTI)

    Biros, George

    2014-08-18

    This the final report for the project "Large-Scale Optimization for Bayesian Inference in Complex Systems," for the work in the group of the co-PI George Biros.

  11. Final Report

    SciTech Connect (OSTI)

    Gurney, Kevin R

    2015-01-12

    This document constitutes the final report under DOE grant DE-FG-08ER64649. The organization of this document is as follows: first, I will review the original scope of the proposed research. Second, I will present the current draft of a paper nearing submission to Nature Climate Change on the initial results of this funded effort. Finally, I will present the last phase of the research under this grant which has supported a Ph.D. student. To that end, I will present the graduate student’s proposed research, a portion of which is completed and reflected in the paper nearing submission. This final work phase will be completed in the next 12 months. This final workphase will likely result in 1-2 additional publications and we consider the results (as exemplified by the current paper) high quality. The continuing results will acknowledge the funding provided by DOE grant DE-FG-08ER64649.

  12. Final Report

    SciTech Connect (OSTI)

    DeTar, Carleton

    2012-12-10

    This document constitutes the Final Report for award DE-FC02-06ER41446 as required by the Office of Science. It summarizes accomplishments and provides copies of scientific publications with significant contribution from this award.

  13. Final Report, Volume 2, The Development of Qualification Standards for Cast Duplex Stainless Steel

    SciTech Connect (OSTI)

    Russell, Steven, W.; Lundin, Carl, W.

    2005-09-30

    The scope of testing cast Duplex Stainless Steel (DSS) required testing to several ASTM specifications, while formulating and conducting industry round robin tests to verify and study the reproducibility of the results. ASTM E562 (Standard Test Method for Determining Volume Fraction by Systematic manual Point Count) and ASTM A923 (Standard Test Methods for Detecting Detrimental Intermetallic Phase in Wrought Duplex Austenitic/Ferritic Stainless Steels) were the specifications utilized in conducting this work. An ASTM E562 industry round robin, ASTM A923 applicability study, ASTM A923 industry round robin, and an ASTM A923 study of the effectiveness of existing foundry solution annealing procedures for producing cast DSS without intermetallic phases were implemented. In the ASTM E562 study, 5 samples were extracted from various cast austenitic and DSS in order to have varying amounts of ferrite. Each sample was metallographically prepared by UT and sent to each of 8 participants for volume fraction of ferrite measurements. Volume fraction of ferrite was measured using manual point count per ASTM E562. FN was measured from the Feritescope�������® and converted to volume fraction of ferrite. Results indicate that ASTM E562 is applicable to DSS and the results have excellent lab-to-lab reproducibility. Also, volume fraction of ferrite conversions from the FN measured by the Feritescope�������® were similar to volume fraction of ferrite measured per ASTM E562. In the ASTM A923 applicability to cast DSS study, 8 different heat treatments were performed on 3 lots of ASTM A890-4A (CD3MN) castings and 1 lot of 2205 wrought DSS. The heat treatments were selected to produce a wide range of cooling rates and hold times in order to study the suitability of ASTM A923 to the response of varying amounts on intermetallic phases [117]. The test parameters were identical to those used to develop ASTM A923 for wrought DSS. Charpy V-notch impact samples were extracted from the castings and wrought DSS and tested per ASTM A923 method B (Charpy impact test). Method A (sodium hydroxide etch test) was performed on one half of a fractured Charpy V-notch impact sample and Method C (ferric chloride corrosion weight loss test) was performed on another half. Test results for the three cast lots and one wrought lot indicate that ASTM A923 is relevant for detecting intermetallic phases in cast DSS. In the ASTM A923 round robin study, five laboratories conducted ASTM A923 Methods A & C on cast DSS material and the lab-to-lab reproducibility of the data was determined. Two groups of samples were sent to the participants. Group 1 samples were tested per ASTM A923 Method A, group 2 samples were tested by ASTM A923 Method C. Testing procedures for this round robin study were identical to those used in the ASTM A923 applicability study. Results from this round robin indicate that there is excellent lab-to-lab reproducibility of ASTM A923 with respect to cast DSS and that ASTM A923 could be expanded to cover both wrought and cast DSS. In the ASTM A923 study of the effectiveness of existing foundry solution annealing procedures for producing cast DSS without intermetallic phases, Ten heats of ASTM A890-4A (CD3MN) in the foundry solution annealed condition were tested per ASTM A923 Methods A, B, & C. Testing of these materials per ASTM A923 was used to determine if the foundry solution anneal procedures were adequate to completely eliminate any intermetallic phases, which may have precipitated during the casting and subsequent heat treatment processes. All heats showed no sign of intermetallic phase per Method A, passed minimum Charpy impact energy requirements per Method B (> 40 ft-lbs @ -40�������°C (-40�������°F)), and showed negligible weight loss per Method C (< 10 mdd). These results indicate that the solution annealing procedure used by foundri

  14. Final Report, Volume 2, The Development of Qualification Standards for Cast Duplex Stainless Steel

    SciTech Connect (OSTI)

    Russell, Steven, W.; Lundin, Carl, D.

    2005-09-30

    The scope of testing cast Duplex Stainless Steel (DSS) required testing to several ASTM specifications, while formulating and conducting industry round robin tests to verify and study the reproducibility of the results. ASTM E562 (Standard Test Method for Determining Volume Fraction by Systematic manual Point Count) and ASTM A923 (Standard Test Methods for Detecting Detrimental Intermetallic Phase in Wrought Duplex Austenitic/Ferritic Stainless Steels) were the specifications utilized in conducting this work. An ASTM E562 industry round robin, ASTM A923 applicability study, ASTM A923 industry round robin, and an ASTM A923 study of the effectiveness of existing foundry solution annealing procedures for producing cast DSS without intermetallic phases were implemented. In the ASTM E562 study, 5 samples were extracted from various cast austenitic and DSS in order to have varying amounts of ferrite. Each sample was metallographically prepared by UT and sent to each of 8 participants for volume fraction of ferrite measurements. Volume fraction of ferrite was measured using manual point count per ASTM E562. FN was measured from the Feritescope{reg_sign} and converted to volume fraction of ferrite. Results indicate that ASTM E562 is applicable to DSS and the results have excellent lab-to-lab reproducibility. Also, volume fraction of ferrite conversions from the FN measured by the Feritescope{reg_sign} were similar to volume fraction of ferrite measured per ASTM E562. In the ASTM A923 applicability to cast DSS study, 8 different heat treatments were performed on 3 lots of ASTM A890-4A (CD3MN) castings and 1 lot of 2205 wrought DSS. The heat treatments were selected to produce a wide range of cooling rates and hold times in order to study the suitability of ASTM A923 to the response of varying amounts on intermetallic phases [117]. The test parameters were identical to those used to develop ASTM A923 for wrought DSS. Charpy V-notch impact samples were extracted from the castings and wrought DSS and tested per ASTM A923 method B (Charpy impact test). Method A (sodium hydroxide etch test) was performed on one half of a fractured Charpy V-notch impact sample and Method C (ferric chloride corrosion weight loss test) was performed on another half. Test results for the three cast lots and one wrought lot indicate that ASTM A923 is relevant for detecting intermetallic phases in cast DSS. In the ASTM A923 round robin study, five laboratories conducted ASTM A923 Methods A & C on cast DSS material and the lab-to-lab reproducibility of the data was determined. Two groups of samples were sent to the participants. Group 1 samples were tested per ASTM A923 Method A, group 2 samples were tested by ASTM A923 Method C. Testing procedures for this round robin study were identical to those used in the ASTM A923 applicability study. Results from this round robin indicate that there is excellent lab-to-lab reproducibility of ASTM A923 with respect to cast DSS and that ASTM A923 could be expanded to cover both wrought and cast DSS. In the ASTM A923 study of the effectiveness of existing foundry solution annealing procedures for producing cast DSS without intermetallic phases, Ten heats of ASTM A890-4A (CD3MN) in the foundry solution annealed condition were tested per ASTM A923 Methods A, B, & C. Testing of these materials per ASTM A923 was used to determine if the foundry solution anneal procedures were adequate to completely eliminate any intermetallic phases, which may have precipitated during the casting and subsequent heat treatment processes. All heats showed no sign of intermetallic phase per Method A, passed minimum Charpy impact energy requirements per Method B (> 40 ft-lbs {at} -40 C (-40 F)), and showed negligible weight loss per Method C (< 10 mdd). These results indicate that the solution annealing procedure used by foundries is adequate to produce a product free from intermetallic phases.

  15. Title 43 CFR 4110: Qualifications and Preference | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page| Open Energy Information Serbia-EnhancingEt Al., 2013)Open EnergyTinoxOpen EnergyInformation 2310: Qualifications

  16. Final Report

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) |Final Report Document Number 11123-23.Final Field

  17. The DOE Advanced Gas Reactor Fuel Development and Qualification Program

    SciTech Connect (OSTI)

    David Petti

    2010-09-01

    The high outlet temperatures and high thermal-energy conversion efficiency of modular High Temperature Gas-cooled Reactors (HTGRs) enable an efficient and cost effective integration of the reactor system with non-electricity generation applications, such as process heat and/or hydrogen production, for the many petrochemical and other industrial processes that require temperatures between 300°C and 900°C. The Department of Energy (DOE) has selected the HTGR concept for the Next Generation Nuclear Plant (NGNP) Project as a transformative application of nuclear energy that will demonstrate emissions-free nuclear-assisted electricity, process heat, and hydrogen production, thereby reducing greenhouse-gas emissions and enhancing energy security. The objective of the DOE Advanced Gas Reactor (AGR) Fuel Development and Qualification program is to qualify tristructural isotropic (TRISO)-coated particle fuel for use in HTGRs. The Advanced Gas Reactor Fuel Development and Qualification Program consists of five elements: fuel manufacture, fuel and materials irradiations, post-irradiation examination (PIE) and safety testing, fuel performance modeling, and fission-product transport and source term evaluation. An underlying theme for the fuel development work is the need to develop a more complete, fundamental understanding of the relationship between the fuel fabrication process and key fuel properties, the irradiation and accident safety performance of the fuel, and the release and transport of fission products in the NGNP primary coolant system. An overview of the program and recent progress is presented.

  18. Qualification tests for {sup 192}Ir sealed sources

    SciTech Connect (OSTI)

    Iancso, Georgeta Iliescu, Elena Iancu, Rodica

    2013-12-16

    This paper describes the results of qualification tests for {sup 192}Ir sealed sources, available in Testing and Nuclear Expertise Laboratory of National Institute for Physics and Nuclear Engineering 'Horia Hulubei' (I.F.I.N.-HH), Romania. These sources had to be produced in I.F.I.N.-HH and were tested in order to obtain the authorization from The National Commission for Nuclear Activities Control (CNCAN). The sources are used for gammagraphy procedures or in gammadefectoscopy equipments. Tests, measurement methods and equipments used, comply with CNCAN, AIEA and International Quality Standards and regulations. The qualification tests are: 1. Radiological tests and measurements: dose equivalent rate at 1 m; tightness; dose equivalent rate at the surface of the transport and storage container; external unfixed contamination of the container surface. 2. Mechanical and climatic tests: thermal shock; external pressure; mechanic shock; vibrations; boring; thermal conditions for storage and transportation. Passing all tests, it was obtained the Radiological Security Authorization for producing the {sup 192}Ir sealed sources. Now IFIN-HH can meet many demands for this sealed sources, as the only manufacturer in Romania.

  19. AGR-3/4 Data Qualification Report for ATR Cycles 151A, 151B, 152A, 152B, 154A, and 154B

    SciTech Connect (OSTI)

    Binh T. Pham

    2014-02-01

    This data report provides the qualification status of Advanced Gas Reactor-3/4 (AGR-3/4) fuel irradiation experimental data from Advanced Test Reactor (ATR) Cycles 151A, 151B, 152A, 152B, 154A, and 154B, as recorded in the Nuclear Data Management and Analysis System (NDMAS). Of these cycles, ATR Cycle 152A is a low power cycle that occurred when the ATR core was briefly at low power. The irradiation data are not used for physics and thermal calculation, but the qualification status of these cycle data is still covered in this report. On the other hand, during ATR Cycles 153A (unplanned Outage cycle) and 153B (Power Axial Locator Mechanism [PALM] cycle), the AGR-3/4 was pulled out from the ATR core and stored in the canal to avoid being overheated. Therefore, qualification of the AGR-3/4 irradiation data from these 2 cycles was excluded in this report. By the end of ATR Cycle 154B, AGR-3/4 was irradiated for a total of 264.1 effective full power days. The AGR-3/4 data streams addressed in this report include thermocouple (TC) temperatures, sweep gas data (flow rates, pressure, and moisture content), and Fission Product Monitoring System (FPMS) data (release rates and release-to-birth rate ratios [R/Bs]) for each of the twelve capsules in the AGR-3/4 experiment. The final data qualification status for these data streams is determined by a Data Review Committee (DRC) composed of AGR technical leads, Sitewide Quality Assurance (QA), and NDMAS analysts. The DRC convened on February 12, 2014, reviewed the data acquisition process, and considered whether the data met the requirements for data collection as specified in QA-approved Very High Temperature Reactor (VHTR) Technology Development Office (TDO) data collection plans. The DRC also examined the results of NDMAS data testing and statistical analyses, and confirmed the qualification status of the data as given in this report.

  20. Final Report

    SciTech Connect (OSTI)

    R. Paul Drake

    2001-11-30

    This final report describes work involving 22 investigators from 11 institutions to explore the dynamics present in supernova explosions by means of experiments on the Omega laser. The specific experiments emphasized involved the unstable expansion of a spherical capsule and the coupling of perturbations at a first interface to a second interface by means of a strong shock. Both effects are present in supernovae. The experiments were performed at Omega and the computer simulations were undertaken at several institutions. B139

  1. EDS V25 containment vessel explosive qualification test report.

    SciTech Connect (OSTI)

    Rudolphi, John Joseph

    2012-04-01

    The V25 containment vessel was procured by the Project Manager, Non-Stockpile Chemical Materiel (PMNSCM) as a replacement vessel for use on the P2 Explosive Destruction Systems. It is the first EDS vessel to be fabricated under Code Case 2564 of the ASME Boiler and Pressure Vessel Code, which provides rules for the design of impulsively loaded vessels. The explosive rating for the vessel based on the Code Case is nine (9) pounds TNT-equivalent for up to 637 detonations. This limit is an increase from the 4.8 pounds TNT-equivalency rating for previous vessels. This report describes the explosive qualification tests that were performed in the vessel as part of the process for qualifying the vessel for explosive use. The tests consisted of a 11.25 pound TNT equivalent bare charge detonation followed by a 9 pound TNT equivalent detonation.

  2. NVLAP ASSESSOR QUALIFICATIONS SUMMARY (REV. 2009-05-07) PAGE 1 National Voluntary Laboratory Accreditation Program

    E-Print Network [OSTI]

    on technical committees and participation in standards development -- 2. Work experience -- provide dates) Experience, such as training given, presentations, technical and standards committee participation Accreditation Program ASSESSOR QUALIFICATIONS SUMMARY Assessors and technical experts play a vital role within

  3. Sample results from the interim salt disposition program macrobatch 9 tank 21H qualification samples

    SciTech Connect (OSTI)

    Peters, T. B.

    2015-11-01

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 9 for the Interim Salt Disposition Program (ISDP). This document reports characterization data on the samples of Tank 21H.

  4. Technical Qualification Program Self-Assessment Report- Sandia Site Office- 2012

    Broader source: Energy.gov [DOE]

    This self assessment examined how Sandia Site Office (SSO) executes the Technical Qualification Program (TQP) as measured by the current Federal Technical Capability Panel criteria review and approach documents (CRADs) included in the assessment plan.

  5. Technical Qualification Program Self-Assessment Report- Livermore Field Office- 2013

    Broader source: Energy.gov [DOE]

    The purpose of the Livermore Field Office (LFO) Teclmical Qualification Program (TQP) is to ensure that federal teclmical personnel with safety oversight responsibilities at defense nuclear facilities at Lawrence Livermore National Laboratory possess competence commensurate with responsibilities.

  6. Final Report

    SciTech Connect (OSTI)

    R Paul Drake

    2004-01-12

    OAK-B135 This is the final report from the project Hydrodynamics by High-Energy-Density Plasma Flow and Hydrodynamics and Radiation Hydrodynamics with Astrophysical Applications. This project supported a group at the University of Michigan in the invention, design, performance, and analysis of experiments using high-energy-density research facilities. The experiments explored compressible nonlinear hydrodynamics, in particular at decelerating interfaces, and the radiation hydrodynamics of strong shock waves. It has application to supernovae, astrophysical jets, shock-cloud interactions, and radiative shock waves.

  7. Final Report

    Office of Scientific and Technical Information (OSTI)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield MunicipalTechnical Report:Speeding accessby aLED Street Lighting FINAL TECHNICAL REPORTFiberProjectto:

  8. Final Proposal

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) | SciTechSubmittedEcologistand9,Final-Proposal Sign In

  9. Final-3

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) |Final Report Document Number(Technical Finaldecisions

  10. FINAL REPORT

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would like submitKansasCommunitiesofExtrans - PermeationGovernment |RoboticFIB7,6,RELEASE FINAL

  11. An analysis of the qualification criteria for small radioactive material shipping packages

    SciTech Connect (OSTI)

    McClure, J.D.

    1983-05-01

    The RAM package design certification process has two important elements, testing and acceptance. These terms sound very similar but they have specific meanings. Qualification testing in the context of this study is the imposition of simulated accident test conditions upon the candidate package design. (Normal transportation environments may also be included.) Following qualification testing, the acceptance criteria provide the performance levels which, if demonstrated, indicate the ability of the RAM package to sustain the severity of the qualification testing sequence and yet maintain specified levels of package integrity. This study has used Severities of Transportation Accidents as a data base to examine the regulatory test criteria which are required to be met by small packages containing Type B quantities of radioactive material (RAM). The basic findings indicate that the present regulatory test standards provide significantly higher levels of protection for the surface transportation modes (truck, rail) than for RAM packages shipped by aircraft. It should also be noted that various risk assessment studies have shown that the risk to the public due to severe transport accidents by surface and air transport modes is very low. A key element in this study was the quantification of the severity of the transportation accident environment and the severity of the present qualification test standards (called qualification test standards in this document) so that a direct comparison could be made between them to assess the effectiveness of the existing qualification test standards. The manner in which this was accomplished is described.

  12. "Order Module--DOE O 426.2, PERSONNEL SELECTION, TRAINING, QUALIFICATION, AND CERTIFICATION REQUIREMENTS FOR DOE NUCLEAR FACILITIES

    Broader source: Energy.gov [DOE]

    "To establish selection, training, qualification, and certification requirements for contractor personnel who can impact the safety basis through their involvement in the operation, maintenance,...

  13. Final Report

    SciTech Connect (OSTI)

    Webb, Robert C.; Kamon, Teruki; Toback, David; Safonov, Alexei; Dutta, Bhaskar; Dimitri, Nanopoulos; Pope, Christopher; White, James

    2013-11-18

    Overview The High Energy Physics Group at Texas A&M University is submitting this final report for our grant number DE-FG02-95ER40917. This grant has supported our wide range of research activities for over a decade. The reports contained here summarize the latest work done by our research team. Task A (Collider Physics Program): CMS & CDF Profs. T. Kamon, A. Safonov, and D. Toback co-lead the Texas A&M (TAMU) collider program focusing on CDF and CMS experiments. Task D: Particle Physics Theory Our particle physics theory task is the combined effort of Profs. B. Dutta, D. Nanopoulos, and C. Pope. Task E (Underground Physics): LUX & NEXT Profs. R. Webb and J. White(deceased) lead the Xenon-based underground research program consisting of two main thrusts: the first, participation in the LUX two-phase xenon dark matter search experiment and the second, detector R&D primarily aimed at developing future detectors for underground physics (e.g. NEXT and LZ).

  14. Analysis and Qualification Documentation The NSTX Upgrade Team

    E-Print Network [OSTI]

    Princeton Plasma Physics Laboratory

    Upgrade Final Design Review (6/22/2011) 4 NSTX CSU Calculation Index Historically What is Available Lodestar MIT Nova Photonics New York U ORNL PPPL Princeton U Purdue U SNL Think Tank, Inc. UC Davis UC Center Stack Upgrade Final Design Review (6/22/2011) Overview · This presentation is an overview

  15. Sample results from the integrated salt disposition program macrobatch 6 tank 21H qualifications MST solids sample

    SciTech Connect (OSTI)

    Peters, T. B.

    2013-02-26

    Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Integrated Salt Disposition Program (ISDP) Batch 6 processing. As part of this qualification work, SRNL performed an Actinide Removal Process (ARP) test. From this test, the residual monosodium titanate (MST) was analyzed for radionuclide uptake. The results of these analyses are reported and are within historical precedent.

  16. DOE handbook: Guide to good practices for the selection, training, and qualification of shift supervisors

    SciTech Connect (OSTI)

    1999-04-01

    This Department of Energy (DOE) handbook is approved for use by all DOE Components and their contractors. The Handbook incorporates editorial changes to DOE-STD-1061-93, ``Guide to Good Practices for the Selection, Training, and Qualification of shift Supervisors,`` and supersedes DOE-STD-1061-93. Technical content of this Handbook has not changed from the original technical standard. Changes are primarily editorial improvements, redesignation of the standard to a Handbook, and format changes to conform with current Technical Standards Program procedures. This guide, used in conjunction with a facility-specific job analysis, provides a framework for the selection, training, qualification, and professional development of reactor facility and non-reactor nuclear facility shift supervisors. Training and qualification programs based on this guide should provide assurance that shift supervisors perform their jobs safely and competently.

  17. SLUDGE BATCH 5 ACCEPTANCE EVALUATION RADIONUCLIDE CONCENTRATIONS IN TANK 51 SB5 QUALIFICATION SAMPLE PREPARED AT SRNL

    SciTech Connect (OSTI)

    Bannochie, C; Ned Bibler, N; David Diprete, D

    2008-07-28

    Presented in this report are radionuclide concentrations required as part of the program of qualifying Sludge Batch Five (SB5) for processing in the Defense Waste Processing Facility (DWPF). Part of this SB5 material is currently in Tank 51 being washed and prepared for transfer to Tank 40. The acceptance evaluation needs to be completed prior to the transfer of the material in Tank 51 to Tank 40 to complete the formation of SB5. The sludge slurry in Tank 40 has already been qualified for DWPF and is currently being processed as SB4. The radionuclide concentrations were measured or estimated in the Tank 51 SB5 Qualification Sample prepared at Savannah River National Laboratory (SRNL). This sample was prepared from the three liter sample of Tank 51 sludge slurry taken on March 21, 2008. The sample was delivered to SRNL where it was initially characterized in the Shielded Cells. Under direction of the Liquid Waste Organization it was then modified by five washes, six decants, an addition of Pu/Be from Canyon Tank 16.4, and an addition of NaNO2. This final slurry now has a composition expected to be similar to that of the slurry in Tank 51 after final preparations have been made for transfer of that slurry to Ta Determining the radionuclide concentrations in this Tank 51 SB5 Qualification Sample is part of the work requested in Technical Task Request (TTR) No. HLW-DWPF-TTR-2008-0010. The work with this qualification sample is covered by a Task Technical and Quality Assurance Plan and an Analytical Study Plan. The radionuclides included in this report are needed for the DWPF Radiological Program Evaluation, the DWPF Waste Acceptance Criteria (TSR/WAC) Evaluation, and the DWPF Solid Waste Characterization Program (TTR Task 2). Radionuclides required to meet the Waste Acceptance Product Specifications (TTR Task 5) will be measured at a later date after the slurry from Tank 51 has been transferred to Tank 40. Then a sample of the as-processed SB5 will be taken and transferred to SRNL for measurement of these radionuclides. Data presented in this report represents the measured or estimated radionuclide concentrations obtained from several standard and special analytical methods performed by Analytical Development (AD) personnel within SRNL. The method for I-129 measurement in sludge is described in detail. Most of these methods were performed on solutions resulting from the dissolutions of the slurry samples. Concentrations are given for twenty-nine radionuclides along with total alpha and beta activity. Values for total gamma and total gamma plus beta activities are also calculated. Results also indicate that 98% of the Tc-99 and 92% of the I-129 that could have been in this sludge batch have been removed by chemical processing steps in the SRS Canyons or Tank Farm.

  18. SLUDGE BATCH 6 ACCEPTANCE EVALUATION: RADIONUCLIDE CONCENTRATIONS IN TANK 51 SB6 QUALIFICATION SAMPLE PREPARED AT SRNL

    SciTech Connect (OSTI)

    Bannochie, C.; Bibler, N.; Diprete, D.

    2010-05-21

    Presented in this report are radionuclide concentrations required as part of the program of qualifying Sludge Batch Six (SB6) for processing in the Defense Waste Processing Facility (DWPF). The SB6 material is currently in Tank 51 being washed and prepared for transfer to Tank 40. The acceptance evaluation needs to be completed prior to the transfer of the material in Tank 51 to Tank 40. The sludge slurry in Tank 40 has already been qualified for DWPF and is currently being processed as SB5. The radionuclide concentrations were measured or estimated in the Tank 51 SB6 Qualification Sample prepared at Savannah River National Laboratory (SRNL). This sample was prepared from the three liter sample of Tank 51 sludge slurry (HTF-51-09-110) taken on October 8, 2009. The sample was delivered to SRNL where it was initially characterized in the Shielded Cells. Under the direction of the Liquid Waste Organization it was then modified by eight washes, nine decants, an addition of Pu from Canyon Tank 16.3, and an addition of NaNO{sub 2}. This final slurry now has a composition expected to be similar to that of the slurry in Tank 51 after final preparations have been made for transfer of that slurry to Tank 40. Determining the radionuclide concentrations in this Tank 51 SB6 Qualification Sample is part of the work requested in Technical Task Request (TTR) No. HLW-DWPF-TTR-2009-0014. The work with this qualification sample is covered by a Task Technical and Quality Assurance Plan and an Analytical Study Plan. The radionuclides included in this report are needed for the DWPF Radiological Program Evaluation, the DWPF Waste Acceptance Criteria (TSR/WAC) Evaluation, and the DWPF Solid Waste Characterization Program (TTR Task I.2). Radionuclides required to meet the Waste Acceptance Product Specifications (TTR Task II.2.) will be measured at a later date after the slurry from Tank 51 has been transferred to Tank 40. Then a sample of the as-processed SB6 will be taken and transferred to SRNL for measurement of these radionuclides. The results presented in this report are those necessary for DWPF to assess if the Tank 51 SB6 sample prepared at SRNL meets the requirements for the DWPF Radiological Program Evaluation, the DWPF Waste Acceptance Criteria evaluation, and the DWPF Solid Waste Characterization Program. The sample is the same as that on which the chemical composition was reported. Concentrations are given for thirty-four radionuclides along with total alpha and beta activity. Values for total gamma and total gamma plus beta activities are also calculated. Results also indicate that 99% of the Tc-99 and at least 90% of the I-129 that could have been in this sludge batch have been removed by chemical processing steps in the SRS Canyons or Tank Farm.

  19. Sample Results from the Interim Salt Disposition Program Macrobatch 6 Tank 21H Qualification Samples

    SciTech Connect (OSTI)

    Peters, T. B.; Fink, S. D.

    2012-12-11

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 6 for the Interim Salt Disposition Project (ISDP). This document reports partial results of the analyses of samples of Tank 21H. No issues with the projected Salt Batch 6 strategy are identified.

  20. Sample Results From The Interim Salt Disposition Program Macrobatch 6 Tank 21H Qualification Samples

    SciTech Connect (OSTI)

    Peters, T. B.; Fink, S. D.

    2012-12-20

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 6 for the Interim Salt Disposition Project (ISDP). This document reports partial results of the analyses of samples of Tank 21H. No issues with the projected Salt Batch 6 strategy are identified.

  1. Personnel Selection, Training, Qualification, and Certification Requirements for DOE Nuclear Facilities

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2010-04-21

    The order establishes selection, training, qualification, and certification requirements for contractor personnel who can impact the safety basis through their involvement in the operation, maintenance, and technical support of Hazard Category 1, 2, and 3 nuclear facilities. Admin Chg 1, dated 7-29-13, supersedes DOE O 426.2.

  2. Personnel Selection, Training, Qualification, and Certification Requirements for DOE Nuclear Facilities

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2010-04-21

    The order establishes selection, training, qualification, and certification requirements for contractor personnel who can impact the safety basis through their involvement in the operation, maintenance, and technical support of Hazard Category 1, 2, and 3 nuclear facilities. Cancels DOE O 5480.20A. Admin Chg 1, dated 7-29-13.

  3. Technical Qualification Program Self-Assessment Report- Carlsbad Field Office- 2012

    Broader source: Energy.gov [DOE]

    Management Assessment (MA-12-08) was conducted from October 1-31, 2012. The management assessment team evaluated the specific requirement implementation, processes, and performance areas of the CBFO Technical Qualification Program (TQP). The assessment covered the relevant parts of DOE 0 426.1, Federal Technical Capability.

  4. Technical Qualification Program Self-Assessment Report- Office of Health, Safety and Security- 2014

    Broader source: Energy.gov [DOE]

    Beginning in April 2014, a self-assessment of the Technical Qualification Program (TQP) was performed in the Office of Health, Safety and Security (HSS). The assessment was led by the HSS TQP Manager who is assigned the responsibility for maintaining and implementing the programs.

  5. (Final Draft) Superconducting

    E-Print Network [OSTI]

    ANDAND (Final Draft) Achieving Advanced Electrical Wires From Superconducting Coatings Prepared and Development Roadmap to Achieve Electrical Wire Advancements from Superconducting Coatings (Final Draft) Edited

  6. Final Exam Information

    E-Print Network [OSTI]

    OwenDavis

    2014-11-28

    MA 22400 FINAL EXAM INFORMATION. The Final Exam is scheduled for Tuesday, December 16, at 7:00 PM in. Lambert Fieldhouse(Indoor Track Area).

  7. Final Exam Memo

    E-Print Network [OSTI]

    math

    2014-12-02

    MA 15910 Final Exam Memo. Final Exam. Tuesday, December 16. 8:00 AM in Lambert Field House. (plan on arriving about 15 minutes early to find your ...

  8. Preliminary Assessment of the Hanford Tank Waste Feed Acceptance and Product Qualification Programs

    SciTech Connect (OSTI)

    Herman, C. C.; Adamson, Duane J.; Herman, D. T.; Peeler, David K.; Poirier, Micheal R.; Reboul, S. H.; Stone, M. E.; Peterson, Reid A.; Chun, Jaehun; Fort, James A.; Vienna, John D.; Wells, Beric E.

    2013-04-01

    The U.S. Department of Energy Office of Environmental Management (EM) is engaging the national laboratories to provide the scientific and technological rigor to support EM program and project planning, technology development and deployment, project execution, and assessment of program outcomes. As an early demonstration of this new responsibility, Savannah River National Laboratory (SRNL) and Pacific Northwest National Laboratory (PNNL) have been chartered to implement a science and technology program addressing Hanford Tank waste feed acceptance and product qualification. As a first step, the laboratories examined the technical risks and uncertainties associated with the planned waste feed acceptance and qualification testing for Hanford tank wastes. Science and technology gaps were identified for work associated with 1) feed criteria development with emphasis on identifying the feed properties and the process requirements, 2) the Tank Waste Treatment and Immobilization Plant (WTP) process qualification program, and 3) the WTP HLW glass product qualification program. Opportunities for streamlining the accetpance and qualification programs were also considered in the gap assessment. Technical approaches to address the science and technology gaps and/or implement the opportunities were identified. These approaches will be further refined and developed as strong integrated teams of researchers from national laboratories, contractors, industry, and academia are brought together to provide the best science and technology solutions. Pursuing the identified approaches will have immediate and long-term benefits to DOE in reducing risks and uncertainties associated with tank waste removal and preparation, transfers from the tank farm to the WTP, processing within the WTP Pretreatment Facility, and in producing qualified HLW glass products. Additionally, implementation of the identified opportunities provides the potential for long-term cost savings given the anticipated facility life of WTP.

  9. Qualification of Innovative High Level Waste Pipeline Unplugging Technologies

    SciTech Connect (OSTI)

    McDaniel, D.; Gokaltun, S.; Varona, J.; Awwad, A.; Roelant, D.; Srivastava, R.

    2008-07-01

    In the past, some of the pipelines have plugged during high level waste (HLW) transfers resulting in schedule delays and increased costs. Furthermore, pipeline plugging has been cited by the 'best and brightest' technical review as one of the major issues that can result in unplanned outages at the Waste Treatment Plant causing inconsistent operation. As the DOE moves toward a more active high level waste retrieval, the site engineers will be faced with increasing cross-site pipeline waste slurry transfers that will result in increased probability of a pipeline getting plugged. Hence, availability of a pipeline unplugging tool/technology is crucial to ensure smooth operation of the waste transfers and in ensuring tank farm cleanup milestones are met. FIU had earlier tested and evaluated various unplugging technologies through an industry call. Based on mockup testing, two technologies were identified that could withstand the rigors of operation in a radioactive environment and with the ability to handle sharp 90 elbows. We present results of the second phase of detailed testing and evaluation of pipeline unplugging technologies and the objective is to qualify these pipeline unplugging technologies for subsequent deployment at a DOE facility. The current phase of testing and qualification comprises of a heavily instrumented 3-inch diameter (full-scale) pipeline facilitating extensive data acquisition for design optimization and performance evaluation, as it applies to three types of plugs atypical of the DOE HLW waste. Furthermore, the data from testing at three different lengths of pipe in conjunction with the physics of the process will assist in modeling the unplugging phenomenon that will then be used to scale-up process parameters and system variables for longer and site typical pipe lengths, which can extend as much as up to 19,000 ft. Detailed information resulting from the testing will provide the DOE end-user with sufficient data and understanding of the technology, and its limitations to aid in the benefit-cost analysis for management decision whether to deploy the technology or to abandon the pipeline as has been done in the past. In conclusion: The ultimate objective of this study is to qualify NuVision's unplugging technology for use at Hanford. Experimental testing has been conducted using three pipeline lengths and three types of blockages. Erosion rates have been obtained and pressure data is being analyzed. An amplification of the inlet pressure has been observed along the pipeline and is the key to determining up to what pipe lengths the technology can be used without surpassing the site pressure limit. In addition, we will attempt to establish what the expected unplugging rates will be at the longer pipe lengths for each of the three blockages tested. Detailed information resulting from the testing will provide the DOE end-user with sufficient data and understanding of the technology, and its limitations so that management decisions can be made whether the technology has a reasonable chance to successfully unplug a pipeline, such as a cross site transfer line or process transfer pipeline at the Waste Treatment Plant. (authors)

  10. Development Of A Macro-Batch Qualification Strategy For The Hanford Tank Waste Treatment And Immobilization Plant

    SciTech Connect (OSTI)

    Herman, Connie C.

    2013-09-30

    The Savannah River National Laboratory (SRNL) has evaluated the existing waste feed qualification strategy for the Hanford Tank Waste Treatment and Immobilization Plant (WTP) based on experience from the Savannah River Site (SRS) Defense Waste Processing Facility (DWPF) waste qualification program. The current waste qualification programs for each of the sites are discussed in the report to provide a baseline for comparison. Recommendations on strategies are then provided that could be implemented at Hanford based on the successful Macrobatch qualification strategy utilized at SRS to reduce the risk of processing upsets or the production of a staged waste campaign that does not meet the processing requirements of the WTP. Considerations included the baseline WTP process, as well as options involving Direct High Level Waste (HLW) and Low Activity Waste (LAW) processing, and the potential use of a Tank Waste Characterization and Staging Facility (TWCSF). The main objectives of the Hanford waste feed qualification program are to demonstrate compliance with the Waste Acceptance Criteria (WAC), determine waste processability, and demonstrate unit operations at a laboratory scale. Risks to acceptability and successful implementation of this program, as compared to the DWPF Macro-Batch qualification strategy, include: Limitations of mixing/blending capability of the Hanford Tank Farm; The complexity of unit operations (i.e., multiple chemical and mechanical separations processes) involved in the WTP pretreatment qualification process; The need to account for effects of blending of LAW and HLW streams, as well as a recycle stream, within the PT unit operations; and The reliance on only a single set of unit operations demonstrations with the radioactive qualification sample. This later limitation is further complicated because of the 180-day completion requirement for all of the necessary waste feed qualification steps. The primary recommendations/changes include the following: Collection and characterization of samples for relevant process analytes from the tanks to be blended during the staging process; Initiation of qualification activities earlier in the staging process to optimize the campaign composition through evaluation from both a processing and glass composition perspective; Definition of the parameters that are important for processing in the WTP facilities (unit operations) across the anticipated range of wastes and as they relate to qualification-scale equipment; Performance of limited testing with simulants ahead of the waste feed qualification sample demonstration as needed to determine the available processing window for that campaign; and Demonstration of sufficient mixing in the staging tank to show that the waste qualification sample chemical and physical properties are representative of the transfers to be made to WTP. Potential flowcharts for derivatives of the Hanford waste feed qualification process are also provided in this report. While these recommendations are an extension of the existing WTP waste qualification program, they are more in line with the processes currently performed for SRS. The implementation of these processes at SRS has been shown to offer flexibility for processing, having identified potential processing issues ahead of the qualification or facility processing, and having provided opportunity to optimize waste loading and throughput in the DWPF.

  11. Final Report, Volume 4, The Develpoment of Qualification Standards forCast Super Duplex Stainless Steel (2507 Wrought Equivalent)

    SciTech Connect (OSTI)

    Hariharan, Vasudevan; Lundin, Carl, D.

    2005-09-30

    The objective of the program is to determine the suitability of ASTM A923 Standard Test methods for Detecting Detrimental Intermetallic Phase in Wrought Duplex Austenitic-Ferritic Stainless Steels for 25 Cr Cast Super Duplex Stainless Steels (ASTM A890-5A). Different tests were carried out on the materials procured from various steel foundries as stated in the ASTM A923. The foundries were designated as Foundry A, B, C and D. All the materials were foundry solution annealed. Materials from Foundry D were solution heat treated at The University of Tennessee also and then they were subjected to heat treatment schedule which was derived from the testing of wrought DSS to establish the A923 specification. This was possible because the material from the same heat was sufficient for conducting the full scope of heat treatment. This was done prior to carrying out various other tests. Charpy samples were machined. The Ferrite content was measured in all the Charpy samples using Feritscope{reg_sign} and ASTM E562 Manual Point Count Method. After the ferrite content was measured the samples were sent to AMC-Vulcan, Inc. in Alabama to conduct the Charpy impact test based on ASTM A923 Test Method B. This was followed by etch testing and corrosion analysis based on ASTM A923 Test Methods A and C respectively at University of Tennessee. Hardness testing using Rockwell B and C was also carried out on these samples. A correlation was derived between all the three test methods and the best method for evaluating the presence of intermetallic in the material was determined. The ferrite content was correlated with the toughness values. Microstructural analysis was carried out on the etch test samples using Scanning Electron Microscopy in order to determine if intermetallic phases were present. The fracture surfaces from Charpy test specimens were also observed under SEM in order to determine the presence of any cracks and whether it was a brittle or a ductile fracture. A correlation was carried out between the ferrite content, hardness values and the type of fracture. SEM was also carried out on the corrosion samples in order to see the difference on the surface after corrosion analysis has been carried out. Energy Dispersive Spectroscopy was carried out on the material acquired from Foundry D in order to determine the variation in the amount of the chemical composition of various elements when the material is subjected to different heat treatment schedules. X-Ray analysis was also carried out in order to verify whether it is possible to identify the different phases present in the material. Volume percentage of ferrite was also calculated from X-Ray diffraction and compared with the Feritscope{reg_sign} and ASTM E562 Manual Point Count data in order to determine whether X-Ray Diffraction is a suitable method for carrying out qualitative analysis of different phases present. From the various tests that were conducted, it was concluded that since ASTM A923 Methods adequately identifies the presence of intermetallic phases in A890-5A grade Cast Super Duplex Stainless Steel A890-5A can be directly included in ASTM A923. Correlation was determined between all the ASTM A923 Test Methods A, B and C and Test Method B were identified as the best method for detecting the presence of detrimental intermetallic phases. The micrographs from the A890-4A grade (now in ASTM A923) were identified as applicable for the A890-5A grade to compare and detect the presence of intermetallic phases. Using these micrographs one can verify whether an A890-5A sample has an unaffected, affected or a possibly affected structure. It was also observed that when compared to the A890-4A grade A890-5A grade is more sensitive to heat treatment. From the ferrite and hardness measurement a correlation was developed between toughness, volume percentage ferrite and hardness of the material. From SEM and EDS the type of intermetallic phase present and its chemical composition was determined. The best method for calculating volume percentage ferrite was determined between the Ferits

  12. Final Report, Volume 4, The Development of Qualification Standards for Cast Super Duplex Stainless Steel (2507 Wrought Equivalent)

    SciTech Connect (OSTI)

    Hariharan, Vasudevan; Lundin, Carl, W.

    2005-09-30

    The objective of the program is to determine the suitability of ASTM A923 ���¢��������Standard Test methods for Detecting Detrimental Intermetallic Phase in Wrought Duplex Austenitic-Ferritic Stainless Steels���¢������� for 25 Cr Cast Super Duplex Stainless Steels (ASTM A890-5A). Different tests were carried out on the materials procured from various steel foundries as stated in the ASTM A923. The foundries were designated as Foundry A, B, C and D. All the materials were foundry solution annealed. Materials from Foundry D were solution heat treated at The University of Tennessee also and then they were subjected to heat treatment schedule which was derived from the testing of wrought DSS to establish the A923 specification. This was possible because the material from the same heat was sufficient for conducting the full scope of heat treatment. This was done prior to carrying out various other tests. Charpy samples were machined. The Ferrite content was measured in all the Charpy samples using Feritscope�������® and ASTM E562 Manual Point Count Method. After the ferrite content was measured the samples were sent to AMC-Vulcan, Inc. in Alabama to conduct the Charpy impact test based on ASTM A923 Test Method B. This was followed by etch testing and corrosion analysis based on ASTM A923 Test Methods A and C respectively at University of Tennessee. Hardness testing using Rockwell B and C was also carried out on these samples. A correlation was derived between all the three test methods and the best method for evaluating the presence of intermetallic in the material was determined. The ferrite content was correlated with the toughness values. Microstructural analysis was carried out on the etch test samples using Scanning Electron Microscopy in order to determine if intermetallic phases were present. The fracture surfaces from Charpy test specimens were also observed under SEM in order to determine the presence of any cracks and whether it was a brittle or a ductile fracture. A correlation was carried out between the ferrite content, hardness values and the type of fracture. SEM was also carried out on the corrosion samples in order to see the difference on the surface after corrosion analysis has been carried out. Energy Dispersive Spectroscopy was carried out on the material acquired from Foundry D in order to determine the variation in the amount of the chemical composition of various elements when the material is subjected to different heat treatment schedules. X-Ray analysis was also carried out in order to verify whether it is possible to identify the different phases present in the material. Volume percentage of ferrite was also calculated from X-Ray diffraction and compared with the Feritscope�������® and ASTM E562 Manual Point Count data in order to determine whether X-Ray Diffraction is a suitable method for carrying out qualitative analysis of different phases present. From the various tests that were conducted, it was concluded that since ASTM A923 Methods adequately identifies the presence of intermetallic phases in A890 ���¢�������� 5A grade Cast Super Duplex Stainless Steel A890 ���¢�������� 5A can be directly included in ASTM A923. Correlation was determined between all the ASTM A923 Test Methods A, B and C and Test Method B were identified as the best method for detecting the presence of detrimental intermetallic phases. The micrographs from the A890-4A grade (now in ASTM A923) were identified as applicable for the A890-5A grade to compare and detect the presence of intermetallic phases. Using these micrographs one can verify whether an A890-5A sample has an unaffected, affected or a possibly

  13. Guide to good practices for training and qualification of instructors. DOE handbook

    SciTech Connect (OSTI)

    1996-03-01

    Purpose of this guide is to provide contractor training organizations with information that can be used to verify the adquacy and/or modify existing instructor training programs, or to develop new training programs. It contains good practices for the training and qualification of technical instructors and instructional technologists at DOE reactor and non-reactor nuclear facilities. It addresses the content of initial and continuing instructor training programs, evaluation of instructor training programs, and maintenance of instructor training records.

  14. SRS SLUDGE BATCH QUALIFICATION AND PROCESSING; HISTORICAL PERSPECTIVE AND LESSONS LEARNED

    SciTech Connect (OSTI)

    Cercy, M.; Peeler, D.; Stone, M.

    2013-09-25

    This report provides a historical overview and lessons learned associated with the SRS sludge batch (SB) qualification and processing programs. The report covers the framework of the requirements for waste form acceptance, the DWPF Glass Product Control Program (GPCP), waste feed acceptance, examples of how the program complies with the specifications, an overview of the Startup Program, and a summary of continuous improvements and lessons learned. The report includes a bibliography of previous reports and briefings on the topic.

  15. GLASS FABRICATION AND ANALYSIS LITERATURE REVIEW AND METHOD SELECTION FOR WTP WASTE FEED QUALIFICATION

    SciTech Connect (OSTI)

    Peeler, D.

    2013-06-27

    Scope of the Report The objective of this literature review is to identify and review documents to address scaling, design, operations, and experimental setup, including configuration, data collection, and remote handling that would be used during waste feed qualification in support of the glass fabrication unit operation. Items addressed include: ? LAW and HLW glass formulation algorithms; ? Mixing and sampling; ? Rheological measurements; ? Heat of hydration; ? Glass fabrication techniques; ? Glass inspection; ? Composition analysis; ? Use of cooling curves; ? Hydrogen generation rate measurement.

  16. Technical Qualification Program Self-Assessment Report- Office of Science- 2013

    Broader source: Energy.gov [DOE]

    Under DOE 426.1, Change 1. Headquarters and Field elements must conduct a self-assessment of Technical Qualification Program (TQP) and Federal Technical Capability Program (FTCP) implementation within their organization at least every four years. These assessments must be conducted in accordance with the requirements of DOE Order (0) 226.1 B, Implementation of Department of Energy Oversight Policy, dated 4-25-11, and the current objectives and criteria approved by the FTCP Chair.

  17. Qualification of data obtained during a severe accident. Illustrative examples from TMI-2 evaluations

    SciTech Connect (OSTI)

    Rempe, Joy L.; Knudson, Darrell L.

    2015-02-01

    The accidents at the Three Mile Island Unit 2 (TMI-2) Pressurized Water Reactor (PWR) and the Daiichi Units 1, 2, and 3 Boiling Water Reactors (BWRs) provide unique opportunities to evaluate instrumentation exposed to severe accident conditions. Conditions associated with the release of coolant and the hydrogen burn that occurred during the TMI-2 accident exposed instrumentation to harsh conditions, including direct radiation, radioactive contamination, and high humidity with elevated temperatures and pressures. Post-TMI-2 instrumentation evaluation programs focused on data required by TMI-2 operators to assess the condition of the reactor and containment and the effect of mitigating actions taken by these operators. Prior efforts also focused on sensors providing data required for subsequent forensic evaluations and accident simulations. This paper provides additional details related to the formal process used to develop a qualified TMI-2 data base and presents data qualification details for three parameters: reactor coolant system (RCS) pressure; containment building temperature; and containment pressure. These selected examples illustrate the types of activities completed in the TMI-2 data qualification process and the importance of such a qualification effort. These details are described to facilitate implementation of a similar process using data and examinations at the Daiichi Units 1, 2, and 3 reactors so that BWR-specific benefits can be obtained.

  18. DOE handbook: Guide to good practices for training and qualification of maintenance personnel

    SciTech Connect (OSTI)

    NONE

    1996-03-01

    The purpose of this Handbook is to provide contractor training organizations with information that can be used to verify the adequacy of and/or modify existing maintenance training programs, or to develop new training programs. This guide, used in conjunction with facility-specific job analyses, provides a framework for training and qualification programs for maintenance personnel at DOE reactor and nonreactor nuclear facilities. Recommendations for qualification are made in four areas: education, experience, physical attributes, and training. The functional positions of maintenance mechanic, electrician, and instrumentation and control technician are covered by this guide. Sufficient common knowledge and skills were found to include the three disciplines in one guide to good practices. Contents include: qualifications; on-the-job training; trainee evaluation; continuing training; training effectiveness evaluation; and program records. Appendices are included which relate to: administrative training; industrial safety training; fundamentals training; tools and equipment training; facility systems and component knowledge training; facility systems and component skills training; and specialized skills training.

  19. SRNL PHASE 1 ASSESSMENT OF THE WAC/DQO AND UNIT OPERATIONS FOR THE WTP WASTE QUALIFICATION PROGRAM

    SciTech Connect (OSTI)

    Peeler, D.; Adamson, D.; Bannochie, C.; Cozzi, A.; Eibling, R.; Hay, M.; Hansen, E.; Herman, D.; Martino, C.; Nash, C.; Pennebaker, F.; Poirier, M.; Reboul, S.; Stone, M.; Taylor-Pashow, K.; White, T.; Wilmarth, B.

    2012-05-16

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is currently transitioning its emphasis from a design and construction phase toward start-up and commissioning. With this transition, the WTP Project has initiated more detailed assessments of the requirements related to actual processing of the Hanford Site tank waste. One particular area of interest is the waste qualification program to be implemented to support the WTP. Given the successful implementation of similar waste qualification efforts at the Savannah River Site (SRS), based on critical technical support and guidance from the Savannah River National Laboratory (SRNL), WTP requested the utilization of subject matter experts from SRNL to support a technology exchange to perform a review of the WTP waste qualification program, discuss the general qualification approach at SRS, and to identify critical lessons learned through the support of DWPF's sludge batch qualification efforts. As part of Phase 1, SRNL subject matter experts in critical technical and/or process areas reviewed specific WTP waste qualification information. The Phase 1 review was a collaborative, interactive, and iterative process between the two organizations. WTP provided specific analytical procedures, descriptions of equipment, and general documentation as baseline review material. SRNL subject matter experts reviewed the information and, as appropriate, requested follow-up information or clarification to specific areas of interest. This process resulted in multiple teleconferences with key technical contacts from both organizations resolving technical issues that lead to the results presented in this report. This report provides the results of SRNL's Phase 1 review of the WAC-DQO waste acceptance criteria and processability parameters, and the specific unit operations which are required to support WTP waste qualification efforts. The review resulted in SRNL providing concurrence, alternative methods, or gap identification for the proposed WTP analytical methods or approaches. For the unit operations, the SRNL subject matter experts reviewed WTP concepts compared to what is used at SRS and provided thoughts on the outlined tasks with respect to waste qualification. Also documented in this report are recommendations and an outline on what would be required for the next phase to further mature the WTP waste qualification program.

  20. Hadronic Final States

    E-Print Network [OSTI]

    B. R. Webber

    1995-10-12

    The following aspects of hadronic final states in deep inelastic lepton scattering are reviewed: measuring $alpha_s$ from multi-jet production rates and event shapes; alternative jet algorithms for DIS; power-suppressed corrections to event shapes; comparing jet fragmentation in $e^+e^-$ annihilation and DIS; final states in the BFKL and CCFM formulations of small-$x$ dynamics; exotic (instanton-induced) final states.

  1. " Million Housing Units, Final...

    U.S. Energy Information Administration (EIA) Indexed Site

    3 Structural and Geographic Characteristics of U.S. Homes, by Year of Construction, 2009" " Million Housing Units, Final" ,,"Year of Construction" ,"Total U.S.1 (millions)"...

  2. National Science Bowl Finals

    ScienceCinema (OSTI)

    None

    2010-09-01

    National Science Bowl finals and awards at the National Building Museum in Washington D.C. Monday 5/3/2010

  3. DOE Final Report

    SciTech Connect (OSTI)

    Hinzman, Larry D.; Long, James; Newby, Greg B.

    2014-01-08

    This final report contains a summary of work accomplished in the establishment of a Climate Data Center at the International Arctic Research Center, University of Alaska Fairbanks.

  4. Final Exam Memo

    E-Print Network [OSTI]

    math

    2011-12-06

    MA 15200 FINAL EXAM Memo. Tuesday, December 13th, 2011, 10:20 AM (2 hour exam). Location: Lambert Fieldhouse. ** Bring your Purdue ID, appropriate

  5. RESULTS OF INITIAL ANALYSES OF THE MACROBATCH 5 TANK 21H QUALIFICATION SAMPLES

    SciTech Connect (OSTI)

    Peters, T.; Fink, S.

    2012-01-31

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Salt (Macro)Batch 5 for the Integrated Salt Disposition Project (ISDP). This document reports the initial results of the analyses of samples of Tank 21H. No issues with the projected Salt Batch 5 strategy are identified. This report describes the laboratory results of Salt (Macro)Batch 5 preliminary samples from Tank 21H. These results will be used by Tank Farm Engineering for their blend calculations. This work was specified by Technical Task Request (TTR) and by Task Technical and Quality Assurance Plan (TTQAP).

  6. Qualification of a Glassy Carbon Blade for a LHC Fast Vacuum Valve

    E-Print Network [OSTI]

    Garion, C

    2013-01-01

    To protect sensitive LHC machine systems against an unexpected gas inrush, a fast vacuum valve system is under development at CERN. The design of the shutter has to be compatible with dynamic loads occurring during the fast closure, namely in the 20 ms range. The material has to fulfil all main requirements such as transparency, high melting temperature, dust free and adequate leak tightness. A development of a blade in vitreous carbon material has been carried out at CERN. The blade has been successfully integrated in a commercial pendulum fast valve. In this paper, the vacuum and mechanical qualification tests are presented.

  7. Results Of Initial Analyses Of The Salt (Macro) Batch 9 Tank 21H Qualification Samples

    SciTech Connect (OSTI)

    Peters, T.

    2015-10-08

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Interim Salt Disposition Project (ISDP) Salt (Macro) Batch 9 for processing through the Actinide Removal Process (ARP) and the Modular Caustic-Side Solvent Extraction Unit (MCU). This document reports the initial results of the analyses of samples of Tank 21H. Analysis of the Tank 21H Salt (Macro) Batch 9 composite sample indicates that the material does not display any unusual characteristics. Further results on the chemistry and other tests will be issued in the future.

  8. Results of initial analyses of the salt (macro) batch 9 tank 21H qualification samples

    SciTech Connect (OSTI)

    Peters, T. B.

    2015-10-01

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Interim Salt Disposition Project (ISDP) Salt (Macro) Batch 9 for processing through the Actinide Removal Process (ARP) and the Modular Caustic-Side Solvent Extraction Unit (MCU). This document reports the initial results of the analyses of samples of Tank 21H. Analysis of the Tank 21H Salt (Macro) Batch 9 composite sample indicates that the material does not display any unusual characteristics or observations, such as floating solids, the presence of large amount of solids, or unusual colors. Further results on the chemistry and other tests will be issued in the future.

  9. Instrument Qualification of Custom Fabricated Water Activity Meter for Hot Cell Use

    SciTech Connect (OSTI)

    McCoskey, Jacob K.

    2014-01-22

    This report describes a custom fabricated water activity meter and the results of the qualification of this meter as described in the laboratory test plan LAB-PLN-11-00012, Testing and Validation of an Enhanced Acquisition and Control System. It was calibrated against several NaOH solutions of varying concentrations to quantify the accuracy and precision of the instrument at 20 °C and 60 °C. Also, a schematic and parts list of the equipment used to make the water activity meter will be presented in this report.

  10. Tank 30 and 37 Supernatant Sample Cross-Check and Evaporator Feed Qualification Analysis-2012

    SciTech Connect (OSTI)

    Oji, L. N.

    2013-03-07

    This report summarizes the analytical data reported by the F/H and Savannah River National Laboratories for the 2012 cross-check analysis for high level waste supernatant liquid samples from SRS Tanks 30 and 37. The intent of this Tank 30 and 37 sample analyses was to perform cross-checks against routine F/H Laboratory analyses (corrosion and evaporator feed qualification programs) using samples collected at the same time from both tanks as well as split samples from the tanks.

  11. SAMPLE RESULTS FROM THE INTEGRATED SALT DISPOSITION PROGRAM MACROBATCH 5 TANK 21H QUALIFICATION SAMPLES

    SciTech Connect (OSTI)

    Peters, T.; Fink, S.

    2012-03-26

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 5 for the Integrated Salt Disposition Project (ISDP). This document reports partial results of the analyses of samples of Tank 21H. No issues with the projected Salt Batch 5 strategy are identified. Results of the analyses of the Tank 21H samples from this report in conjunction with the findings of the previous report, indicates that the material does not display any unusual characteristics.

  12. Microsoft Word - Final TEC Notes_April 2005.doc

    Office of Environmental Management (EM)

    training for all elements of the process, as well as personnel qualification testing. He said that the utility performed dry runs of the process, which included NRC...

  13. Final Technical Report

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) |Final Report Document Number(Technical Final Final Tank015

  14. Qualification Requirements of Guided Ultrasonic Waves for Inspection of Piping in Light Water Reactors

    SciTech Connect (OSTI)

    Meyer, Ryan M.; Ramuhalli, Pradeep; Doctor, Steven R.; Bond, Leonard J.

    2013-08-01

    Guided ultrasonic waves (GUW) are being increasingly used for both NDT and monitoring of piping. GUW offers advantages over many conventional NDE technologies due to the ability to inspect large volumes of piping components without significant removal of thermal insulation or protective layers. In addition, regions rendered inaccessible to more conventional NDE technologies may be more accessible using GUW techniques. For these reasons, utilities are increasingly considering the use of GUWs for performing the inspection of piping components in nuclear power plants. GUW is a rapidly evolving technology and its usage for inspection of nuclear power plant components requires refinement and qualification to ensure it is able to achieve consistent and acceptable levels of performance. This paper will discuss potential requirements for qualification of GUW techniques for the inspection of piping components in light water reactors (LWRs). The Nuclear Regulatory Commission has adopted ASME Boiler and Pressure Vessel Code requirements in Sections V, III, and XI for nondestructive examination methods, fabrication inspections, and pre-service and in-service inspections. A Section V working group has been formed to place the methodology of GUW into the ASME Boiler and Pressure Vessel Code but no requirements for technique, equipment, or personnel exist in the Code at this time.

  15. Examination of a Junction-Box Adhesion Test for Use in Photovoltaic Module Qualification: Preprint

    SciTech Connect (OSTI)

    Miller, D. C.; Wohlgemuth, J. H.

    2012-08-01

    Engineering robust adhesion of the junction-box (j-box) is a hurdle typically encountered by photovoltaic (PV) module manufacturers during product development. There are historical incidences of adverse effects (e.g., fires) caused when the j-box/adhesive/module system has failed in the field. The addition of a weight to the j-box during the 'damp heat' IEC qualification test is proposed to verify the basic robustness of its adhesion system. The details of the proposed test will be described, in addition to the preliminary results obtained using representative materials and components. The described discovery experiments examine moisture-cured silicone, foam tape, and hot-melt adhesives used in conjunction with PET or glass module 'substrates.' To be able to interpret the results, a set of material-level characterizations was performed, including thermogravimetric analysis, differential scanning calorimetry, and dynamic mechanical analysis. PV j-boxes were adhered to a substrate, loaded with a prescribed weight, and then placed inside an environmental chamber (at 85C, 85% relative humidity). Some systems did not remain attached through the discovery experiments. Observed failure modes include delamination (at the j-box/adhesive or adhesive/substrate interface) and phase change/creep. The results are discussed in the context of the application requirements, in addition to the plan for the formal experiment supporting the proposed modification to the qualification test.

  16. " Million Housing Units, Final...

    U.S. Energy Information Administration (EIA) Indexed Site

    2 Water Heating in U.S. Homes, by OwnerRenter Status, 2009" " Million Housing Units, Final" ,,,,"Housing Unit Type" ,,,,"Single-Family Units",,,,"Apartments in Buildings With"...

  17. " Million Housing Units, Final...

    U.S. Energy Information Administration (EIA) Indexed Site

    3 Computers and Other Electronics in U.S. Homes, by Year of Construction, 2009" " Million Housing Units, Final" ,,"Year of Construction" ,"Total U.S.1 (millions)" ,,"Before...

  18. " Million Housing Units, Final...

    U.S. Energy Information Administration (EIA) Indexed Site

    3 Household Demographics of U.S. Homes, by Year of Construction, 2009" " Million Housing Units, Final" ,,"Year of Construction" ,"Total U.S.1 (millions)" ,,"Before 1940","1940 to...

  19. " Million Housing Units, Final...

    U.S. Energy Information Administration (EIA) Indexed Site

    3 Space Heating in U.S. Homes, by Year of Construction, 2009" " Million Housing Units, Final" ,,"Year of Construction" ,"Total U.S.1 (millions)" ,,"Before 1940","1940 to...

  20. " Million Housing Units, Final...

    U.S. Energy Information Administration (EIA) Indexed Site

    3 Air Conditioning in U.S. Homes, by Year of Construction, 2009" " Million Housing Units, Final" ,,"Year of Construction" ,"Total U.S.1 (millions)" ,,"Before 1940","1940 to...

  1. " Million Housing Units, Final...

    U.S. Energy Information Administration (EIA) Indexed Site

    3 Fuels Used and End Uses in U.S. Homes, by Year of Construction, 2009" " Million Housing Units, Final" ,,"Year of Construction" ,"Total U.S.1 (millions)" ,,"Before 1940","1940 to...

  2. Aurora final report

    SciTech Connect (OSTI)

    Robert, Dross; Amedeo, Conti

    2013-12-06

    Final Technical report detailing the work done by Nuvera and its partners to fulfill the goals of the program "Transport Studies Enabling Efficiency Optimization of Cost-Competitive Fuel Cell Stacks" (a.k.a. AURORA)

  3. Study Sheet for Final

    E-Print Network [OSTI]

    2015-04-30

    MA351 Final Exam Study Sheet. The exam covers Chapter 3, only Section 3.5, except for p. 232 and 233,. Chapter 5, all sections, but none of the subsections, ...

  4. Qualification of the First ICS-3000 ION Chromatograph for use at the Defense Waste Processing Facility

    SciTech Connect (OSTI)

    Edwards, T; Mahannah, R.

    2011-07-05

    The ICS-3000 Ion Chromatography (IC) system installed in 221-S M-13 has been qualified for use. The qualification was a head to head comparison of the ICS-3000 with the currently used DX-500 IC system. The crosscheck work included standards for instrument calibration and calibration verifications and standards for individual anion analysis, where the standards were traceable back to the National Institute of Standards and Technology (NIST). In addition the crosscheck work included the analysis of simulated Sludge Receipt Adjustment Tank (SRAT) Receipt, SRAT Product, and Slurry Mix Evaporator (SME) samples, along with radioactive Sludge Batch 5 material from the SRAT and SME tanks. Based upon the successful qualification of the ICS-3000 in M-13, it is recommended that this task proceed in developing the data to qualify, by a head to head comparison of the two ICS-3000 instruments, a second ICS-3000 to be installed in M-14. The Defense Waste Processing Facility (DWPF) requires the analysis of specific anions at various stages of its processing of high level waste (HLW). The anions of interest to the DWPF are fluoride, formate, chloride, nitrite, nitrate, sulfate, oxalate, and phosphate. The anion analysis is used to evaluate process chemistry including formic acid/nitric acid additions to establish optimum conditions for mercury stripping, reduction-oxidation (REDOX) chemistry for the melter, nitrite destruction, organic acid constituents, etc. The DWPF Laboratory (Lab) has been using Dionex DX-500 ion chromatography (IC) systems since 1998. The vendor informed DWPF in 2006 that the instruments would no longer be supported by service contracts after 2008. DWPF purchased three new ICS-3000 systems in September of 2006. The ICS-3000 instruments are (a) designed to be more stable using an eluent generator to make eluent, (b) require virtually no daily chemical handling by the analysts, (c) require less line breaks in the hood, and (d) generally require less maintenance due to the pump configuration only using water versus the current system where the pump uses various hydroxide concentrations. The ICS-3000 instruments also allow the DWPF to maintain current service contracts, which support routine preventive maintenance and emergency support for larger problems such as component failure. One of the three new systems was set up in the DWPF Lab trailers in January of 2007 to be used for the development of methods and procedures. This system will continue to be used for training, new method development and potential improvements to current methods. The qualification of the other two ICS-3000 instruments is to be a phased effort. This effort is to be supported by the Applied Computational Engineering and Statistical (ACES) group of the Savannah River National Laboratory (SRNL) as authorized by the Technical Task Request (TTR) and as directed by the corresponding Task Technical and Quality Assurance (TT&QA) plan. The installation of the first 'rad' system into the M-13 Lab module required modifications to both the Lab module and to the radiohood. The installation was completed in July 2008. The testing of this system was conducted as directed by the TT&QA plan. The purpose of this technical report is to provide a review of the data generated by these tests that will lead to the recommendation for the qualification of the M-13 ICS-3000 instrument. With the successful qualification of this first ICS-3000, plans will be developed for the installation of the second 'rad' system in the M-14 Lab module later in fiscal year 2009. When the second 'rad' ICS-3000 system is installed, the DX-500 systems will be removed and retired from service.

  5. CESAR5.3: An Industrial Tool for Nuclear Fuel and Waste Characterization with Associated Qualification - 12067

    SciTech Connect (OSTI)

    Vidal, Jean-Marc; Eschbach, Romain [CEA, DEN, DER, SPRC, LECy, Cadarache, F-13108 Saint-Paul-lez-Durance (France); Launay, Agnes; Binet, Christophe [AREVA-NC La Hague, F-50444 Beaumont-Hague (France); THRO, Jean-Francois [AREVA-NC BU Recyclage, Tour AREVA, F-92084 Paris-La-Defense (France)

    2012-07-01

    CEA and AREVA-NC have developed and used a depletion code named CESAR for 30 years. This user-friendly industrial tool provides fast characterizations for all types of nuclear fuel (PWR / UOX or MOX or reprocess Uranium, BWR / UOX or MOX, MTR and SFR) and the wastes associated. CESAR can evaluate 100 heavy nuclides, 200 fission products and 150 activation products (with Helium and Tritium formation). It can also characterize the structural material of the fuel (Zircalloy, stainless steel, M5 alloy). CESAR provides depletion calculations for any reactor irradiation history and from 3 months to 1 million years of cooling time. CESAR5.3 is based on the latest calculation schemes recommended by the CEA and on an international nuclear data base (JEFF-3.1.1). It is constantly checked against the CEA referenced and qualified depletion code DARWIN. CESAR incorporates the CEA qualification based on the dissolution analyses of fuel rod samples and the 'La Hague' reprocessing plant feedback experience. AREVA-NC uses CESAR intensively at 'La Hague' plant, not only for prospective studies but also for characterizations at different industrial facilities all along the reprocessing process and waste conditioning (near 150 000 calculations per year). CESAR is the reference code for AREVA-NC. CESAR is used directly or indirectly with other software, data bank or special equipment in many parts of the La Hague plants. The great flexibility of CESAR has rapidly interested other projects. CESAR became a 'tool' directly integrated in some other softwares. Finally, coupled with a Graphical User Interface, it can be easily used independently, responding to many needs for prospective studies as a support for nuclear facilities or transport. An English version is available. For the principal isotopes of U and Pu, CESAR5 benefits from the CEA experimental validation for the PWR UOX fuels, up to a burnup of 60 GWd/t and for PWR MOX fuels, up to 45 GWd/t. CESAR version 5.3 uses the CEA reference calculation codes for neutron physics with the JEFF-3.1.1 nuclear data set. (authors)

  6. UC Fire Engineering Programme Structure The programme awards four qualifications: Doctor of Philosophy (PhD) in Fire

    E-Print Network [OSTI]

    Hickman, Mark

    UC Fire Engineering Programme Structure The programme awards four qualifications: Doctor of Philosophy (PhD) in Fire Engineering, Master of Engineering in Fire Engineering (MEFE), Master of Engineering Studies in Fire Engineering (MEngSt(Fire)) and a Postgraduate Certificate in Fire Engineering (PGCert(Fire

  7. ePUB: Modellierung Molecular Life Sciences Master Major 90 ECTS-Credits with special qualification in Biochemistry/

    E-Print Network [OSTI]

    Richner, Heinz

    in Biochemistry/ Chemical Biology [Reglement 01.10.2005] Seite 1 1. Teil: Struktur des Studiums (Prüfungsfächer) Offizieller Abschluss: Master of Science in Molecular Life Sciences with special qualification in Biochemistry/Chemical Biology, Universität Bern ePUB - interne Bezeichnung: MLS M Major 90 ECTS Biochemistry/Chemical Biology

  8. Data Qualification Report: Calculated Porosity and Porosity-Derived Values for Lithostratigraphic Units for use on the Yucca Mountain Project

    SciTech Connect (OSTI)

    P. Sanchez

    2001-05-30

    The qualification is being completed in accordance with the Data Qualification Plan DQP-NBS-GS-000006, Rev. 00 (CRWMS M&O 2001). The purpose of this data qualification activity is to evaluate for qualification the unqualified developed input and porosity output included in Data Tracking Number (DTN) M09910POROCALC.000. The main output of the analyses documented in DTN M09910POROCALC.000 is the calculated total porosity and effective porosity for 40 Yucca Mountain Project boreholes. The porosity data are used as input to Analysis Model Report (AMR) 10040, ''Rock Properties Model'' (MDL-NBS-GS-000004, Rev. 00), Interim Change Notice [ICN] 02 (CRWMS M&O 2000b). The output from the rock properties model is used as input to numerical physical-process modeling within the context of a relationship developed in the AMR between hydraulic conductivity, bound water and zeolitic zones for use in the unsaturated zone model. In accordance with procedure AP-3.15Q, the porosity output is not used in the direct calculation of Principal Factors for post-closure safety or disruptive events. The original source for DTN M09910POROCALC.000 is a Civilian Radioactive Waste Management System (CRWMS) Management and Operating Contractor (M&O) report, ''Combined Porosity from Geophysical Logs'' (CRWMS M&O 1999a and hereafter referred to as Rael 1999). That report recalculated porosity results for both the historical boreholes covered in Nelson (1996), and the modern boreholes reported in CRWMS M&O (1996a,b). The porosity computations in Rael (1999) are based on density-porosity mathematical relationships requiring various input parameters, including bulk density, matrix density and air and/or fluid density and volumetric water content. The main output is computed total porosity and effective porosity reported on a foot-by-foot basis for each borehole, although volumetric water content is derived from neutron data as an interim output. This qualification report uses technical assessment and corroboration to evaluate the original subject DTN. Rael (1999) provides many technical details of the technical assessment and corroboration methods and partially satisfies the intent of the qualification plan for this analysis. Rael presents a modified method based on Nelson (1996) to recompute porosity and porosity-derived values and uses some of the same inputs. Rael's (1999) intended purpose was to document porosity output relatively free of biases introduced by differing computational methods or parameter selections used for different boreholes. The qualification report necessarily evaluates the soundness of the pre-Process Validation and Re-engineering (PVAR) analyses and methodology, as reported in Rael (1999).

  9. Data Qualification Report For: Thermodynamic Data File, DATA0.YMP.R0 For Geochemical Code, EQ3/6 

    SciTech Connect (OSTI)

    P.L. Cloke

    2001-10-16

    The objective of this work is to evaluate the adequacy of chemical thermodynamic data provided by Lawrence Livermore National Laboratory (LLNL) as DataO.ymp.ROA in response to an input request submitted under AP-3.14Q. This request specified that chemical thermodynamic data available in the file, Data0.com.R2, be updated, improved, and augmented for use in geochemical modeling used in Process Model Reports (PMRs) for Engineered Barrier Systems, Waste Form, Waste Package, Unsaturated Zone, and Near Field Environment, as well as for Performance Assessment. The data are qualified in the temperature range 0 to 100 C. Several Data Tracking Numbers (DTNs) associated with Analysis/Model Reports (AMR) addressing various aspects of the post-closure chemical behavior of the waste package and the Engineered Barrier System that rely on EQ316 outputs to which these data are used as input, are Principal Factor affecting. This qualification activity was accomplished in accordance with the AP-SIII.2Q using the Technical Assessment method. A development plan, TDP-EBS-MD-000044, was prepared in accordance with AP-2.13Q and approved by the Responsible Manager. In addition, a Process Control Evaluation was performed in accordance with AP-SV.1Q. The qualification method, selected in accordance with AP-SIII.2Q, was Technical Assessment. The rationale for this approach is that the data in File Data0.com.R2 are considered Handbook data and therefore do not themselves require qualification. Only changes to Data0.com.R2 required qualification. A new file has been produced which contains the database Data0.ymp.R0, which is recommended for qualification as a result of this action. Data0.ymp.R0 will supersede Data0.com.R2 for all Yucca Mountain Project (YMP) activities.

  10. Qualification of the Nippon Instrumentation for use in Measuring Mercury at the Defense Waste Processing Facility

    SciTech Connect (OSTI)

    Edwards, T.; Mahannah, R.

    2011-07-05

    The Nippon Mercury/RA-3000 system installed in 221-S M-14 has been qualified for use. The qualification was a side-by-side comparison of the Nippon Mercury/RA-3000 system with the currently used Bacharach Mercury Analyzer. The side-by-side testing included standards for instrument calibration verifications, spiked samples and unspiked samples. The standards were traceable back to the National Institute of Standards and Technology (NIST). The side-by-side work included the analysis of Sludge Receipt and Adjustment Tank (SRAT) Receipt, SRAT Product, and Slurry Mix Evaporator (SME) samples. With the qualification of the Nippon Mercury/RA-3000 system in M-14, the DWPF lab will be able to perform a head to head comparison of a second Nippon Mercury/RA-3000 system once the system is installed. The Defense Waste Processing Facility (DWPF) analyzes receipt and product samples from the Sludge Receipt and Adjustment Tank (SRAT) to determine the mercury (Hg) concentration in the sludge slurry. The SRAT receipt is typically sampled and analyzed for the first ten SRAT batches of a new sludge batch to obtain an average Hg concentration. This average Hg concentration is then used to determine the amount of steam stripping required during the concentration/reflux step of the SRAT cycle to achieve a less than 0.6 wt% Hg in the SRAT product solids. After processing is complete, the SRAT product is sampled and analyzed for mercury to ensure that the mercury concentration does not exceed the 0.45 wt% limit in the Slurry Mix Evaporator (SME). The DWPF Laboratory utilizes Bacharach Analyzers to support these Hg analyses at this facility. These analyzers are more than 10 years old, and they are no longer supported by the manufacturer. Due to these difficulties, the Bacharach Analyzers are to be replaced by new Nippon Mercury/RA-3000 systems. DWPF issued a Technical Task Request (TTR) for the Savannah River National Laboratory (SRNL) to assist in the qualification of the new systems. SRNL prepared a task technical and quality assurance (TT&QA) plan that outlined the activities that are necessary and sufficient to meet the objectives of the TTR. In addition, TT&QA plan also included a test plan that provided guidance to the DWPF Lab in collecting the data needed to qualify the new Nippon Mercury/RA-3000 systems.

  11. Final Design Completion The Comprehensive Final Design Review1

    E-Print Network [OSTI]

    Princeton Plasma Physics Laboratory

    Final Design Completion The Comprehensive Final Design Review1 (CFDR) marks the end of the final (detailed) design phase of system design. At this point, the system design should be defined in drawings and specifications. The CFDR will likely have been preceded by component/subassembly Final Design Reviews (FDRs

  12. Results Of Initial Analyses Of The Macrobatch 7 Tank 21H Qualification Samples

    SciTech Connect (OSTI)

    Peters, T. B.; Washington, A. L. II

    2013-07-08

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Salt (Macro) Batch 7 for the Interim Salt Disposition Program (ISDP) through ARP/MCU. This document reports the initial results of the analyses of samples of Tank 21H. Further results on the chemistry and other tests will be issued in the future. No issues with the projected Salt Batch 7 strategy are identified, other than the presence of visible quantities of dark colored solids. Based upon a SRNL settling test, the solids should settle well within the months-long settling period to be employed in Tank 21H. However, SRNL recommends analyzing the solids to provide input to OLI modeling in order to evaluate the impacts of these solids to present and future salt batches.

  13. A NEW SIMULATION FRAMEWORK BASED ON THE KEPLER AND SCICOS OPEN-SOURCE SOFTWARE FOR THE DESIGN AND QUALIFICATION OF TOKAMAK CONTROL ALGORITHMS

    E-Print Network [OSTI]

    Vallette, Bruno

    AND QUALIFICATION OF TOKAMAK CONTROL ALGORITHMS: FIRST TEST CASE RESULTS Oliviero Barana1 , Cédric Boulbe2 , Sylvain I. INTRODUCTION ITER1,2 will be the most complex and powerful tokamak device ever built in the field

  14. Final Technical Report

    SciTech Connect (OSTI)

    Gilbert, Chris

    2014-11-13

    The project, ?Capital Investment to Fund Equipment Purchases and Facility Modifications to Create a Sustainable Future for EnergyXchange? served to replace landfill gas energy with alternative energy resources, primarily solar and wood waste. This is the final project closeout report.

  15. Sustainable energy Examen Final

    E-Print Network [OSTI]

    Ernst, Damien

    Sustainable energy Examen Final 24 mai 2013 Consignes ­ Vous disposez de 2 heures 30. ­ N'air. (2 points) [C] A partir de l`a, proposez une expression math´ematique permettant de calculer l'´energie pour pouvoir minimiser sa consommation en ´energie. (1 point) [E] Calculez le minimum d'´energie

  16. Sustainable energy Examen Final

    E-Print Network [OSTI]

    Ernst, Damien

    Sustainable energy Examen Final 3 juin 2015 Consignes -- Vous disposez de 2h30. -- N'oubliez pas de a discut´e au cours de son expos´e intitul´e "Une histoire d'´energie : ´equations et transition" du fait que la prosp´erit´e des civilisations est intrins`equement li´ee `a leur consommation d'´energie

  17. Final Report Sustainability at

    E-Print Network [OSTI]

    Escher, Christine

    1 Final Report Sustainability at Oregon State University Prepared by The Institute for Natural Resources Oregon State University June 2009 #12;2 Sustainability at Oregon State University June 2009 The Institute for Natural Resources Created by the Oregon Legislature through the 2001 Oregon Sustainability Act

  18. Final Scientific/Technical Report

    SciTech Connect (OSTI)

    Troxell, W; Batchelor, A

    2012-11-28

    Final report for the formation of faculty and education establishing Colorado State's Smart Grid Integration Center

  19. Final Technical Report

    SciTech Connect (OSTI)

    Maxwell, Mike, J., P.E.

    2012-08-30

    The STI product is the Final Technical Report from ReliOn, Inc. for contract award DE-EE0000487: Recovery Act PEM Fuel Cell Systems Providing Emergency Reserve and Backup Power. The program covered the turnkey deployment of 431 ReliOn fuel cell systems at 189 individual sites for AT&T and PG&E with ReliOn functioning as the primary equipment supplier and the project manager. The Final Technical Report provides an executive level summary, a comparison of the actual accomplishments vs. the goals and objectives of the project, as well as a summary of the project activity from the contract award date of August 1, 2009 through the contract expiration date of December 31, 2011. Two photos are included in the body of the report which show hydrogen storage and bulk hydrogen refueling technologies developed as a result of this program.

  20. Sustainable energy Examen Final

    E-Print Network [OSTI]

    Ernst, Damien

    Sustainable energy Examen Final 30 mai 2014 Consignes -- Vous disposez de 2 heures 30. -- N produire une quantit´e d'´energie ´equivalente `a la quantit´e d'´energie ´electrique consomm´ee par un) La mise `a disposition d'´energie dans une soci´et´e n´ecessite elle-m^eme de l'´energie. Dans la lit

  1. Sample Results From The Interim Salt Disposition Program Macrobatch 7 Tank 21H Qualification MST Solids Sample

    SciTech Connect (OSTI)

    Washington, A. L. II; Peters, T. B.

    2013-09-19

    Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Interim Salt Disposition Program (ISDP) Batch 7 processing. The Marcrobatch 7 material was received with visible fine particulate solids, atypical for these samples. The as received material was allowed to settle for a period greater than 24 hours. The supernatant was then decanted and utilized as our clarified feed material. As part of this qualification work, SRNL performed an Actinide Removal Process (ARP) test using the clarified feed material. From this test, the residual monosodium titanate (MST) was analyzed for radionuclide uptake after filtration from H-Tank Farm (HTF) feed salt solution. The results of these analyses are reported and are within historical precedent.

  2. SAMPLE RESULTS FROM THE INTEGRATED SALT DISPOSITION PROGRAM MACROBATCH 5 TANK 21H QUALIFICATION MST, ESS AND PODD SAMPLES

    SciTech Connect (OSTI)

    Peters, T.; Fink, S.

    2012-04-24

    Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Integrated Salt Disposition Program (ISDP) Batch 5 processing. This qualification material was a composite created from recent samples from Tank 21H and archived samples from Tank 49H to match the projected blend from these two tanks. Additionally, samples of the composite were used in the Actinide Removal Process (ARP) and extraction-scrub-strip (ESS) tests. ARP and ESS test results met expectations. A sample from Tank 21H was also analyzed for the Performance Objectives Demonstration Document (PODD) requirements. SRNL was able to meet all of the requirements, including the desired detection limits for all the PODD analytes. This report details the results of the Actinide Removal Process (ARP), Extraction-Scrub-Strip (ESS) and Performance Objectives Demonstration Document (PODD) samples of Macrobatch (Salt Batch) 5 of the Integrated Salt Disposition Program (ISDP).

  3. FPGA and Software Design for the Qualification and Automated tests for the production of CERN Digital Acquisition Boards

    E-Print Network [OSTI]

    Laroussi, H; Lefevre, T; Degeest, A; Garcia, S; Tichon, J

    The VFC-HPC is an FPGA-based multipurpose board designed to be the new standard back-end for the Beam Instrumentation (BI) Group. This contribution is aimed to give a presentation of the test and qualification system designed to be used to verify the compliance of the VFC-HPC to the specifications. We will begin by presenting the CERN, the company, its main purpose and its brief history. Afterward, we will present the VFC-HPC, the purpose of this board and its mains characteristics. We will then focus on the work done to allow the test and qualification of the VFC-HPC. This project was focused on the test and qualification of the connectivity of the board, consisting of the FMC Connector and the SFPs. This work involved making several market surveys to choose the proper test components to be used (as FMC Mezzanines), setting up a test bench, implementing optical communications through SFPs, writing Verilog firmwares, writing software test routines in Python and measuring Bit Error Rates (BER) and eye diagrams...

  4. AGR-2 Data Qualification Report for ATR Cycles 147A, 148A, 148B, and 149A

    SciTech Connect (OSTI)

    Michael L. Abbott; Keith A. Daum

    2011-08-01

    This report presents the data qualification status of fuel irradiation data from the first four reactor cycles (147A, 148A, 148B, and 149A) of the on-going second Advanced Gas Reactor (AGR-2) experiment as recorded in the NGNP Data Management and Analysis System (NDMAS). This includes data received by NDMAS from the period June 22, 2010 through May 21, 2011. AGR-2 is the second in a series of eight planned irradiation experiments for the AGR Fuel Development and Qualification Program, which supports development of the very high temperature gas-cooled reactor (VHTR) under the Next Generation Nuclear Plant (NGNP) Project. Irradiation of the AGR-2 test train is being performed at the Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL) and is planned for 600 effective full power days (approximately 2.75 calendar years) (PLN-3798). The experiment is intended to demonstrate the performance of UCO (uranium oxycarbide) and UO2 (uranium dioxide) fuel produced in a large coater. Data qualification status of the AGR-1 experiment was reported in INL/EXT-10-17943 (Abbott et al. 2010).

  5. DOE Laminar Final Report

    Office of Scientific and Technical Information (OSTI)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield MunicipalTechnical Report:Speeding accessby a contractorEnergy,DEC03t933 OSTlandFinal Technical

  6. Final Technical Report

    Office of Scientific and Technical Information (OSTI)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield MunicipalTechnical Report:Speeding accessby aLED Street Lighting FINAL TECHNICAL REPORTFiber Technical

  7. Final Technical Report Division

    Office of Scientific and Technical Information (OSTI)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield MunicipalTechnical Report:Speeding accessby aLED Street Lighting FINAL TECHNICALNumerical

  8. Blackout Final Implementation Report

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergyTher i n c i p a l De pEnergy Industrial Local GovernmentDepartment ofFinal

  9. Proposal for Qualification of Gas-Generating Radioactive Payloads for Transportation within a Type B Package

    SciTech Connect (OSTI)

    Houghtaling, T.K.

    2002-06-07

    Characterization data describing radioactive materials (RAM) in storage are likely those associated with the processes that produced the materials or with the mission for which they were produced. Along with impurity data, often absent or unknown as a result of post-processing storage environment is moisture content. Radiolysis of moisture may lead to a hydrogen flammability hazard within a closed volume such as a storage can or a transportation package. This paper offers a practical means of qualifying payloads of unknown moisture content for shipment within Type B packaging, while supporting the DOE program to maintain radworker dose as low as reasonable achievable (ALARA). Specifically, the paper discusses part of a qualification program carried out at the Savannah River Site for onsite shipment of legacy RAM within the DDF-1 package. The DDF-1 is an onsite-only prototype of the currently certified 9975 package. Measurement of storage-can lid bulge can provide an upper bound for pressure within a storage can. Subsequent belljar testing can measure the rate of gas leakage from a storage can. These actions are shown sufficient to ensure that the performance of the 9975 containment vessels can accommodate the deflagration energy from flammable gas mixtures within Normal Conditions of Transport, and, and the consequences of a detonation shock wave within Hypothetical Accident Conditions.

  10. Reactor Testing and Qualification: Prioritized High-level Criticality Testing Needs

    SciTech Connect (OSTI)

    S. Bragg-Sitton; J. Bess; J. Werner; G. Harms; S. Bailey

    2011-09-01

    Researchers at the Idaho National Laboratory (INL) were tasked with reviewing possible criticality testing needs to support development of the fission surface power system reactor design. Reactor physics testing can provide significant information to aid in development of technologies associated with small, fast spectrum reactors that could be applied for non-terrestrial power systems, leading to eventual system qualification. Several studies have been conducted in recent years to assess the data and analyses required to design and build a space fission power system with high confidence that the system will perform as designed [Marcille, 2004a, 2004b; Weaver, 2007; Parry et al., 2008]. This report will provide a summary of previous critical tests and physics measurements that are potentially applicable to the current reactor design (both those that have been benchmarked and those not yet benchmarked), summarize recent studies of potential nuclear testing needs for space reactor development and their applicability to the current baseline fission surface power (FSP) system design, and provide an overview of a suite of tests (separate effects, sub-critical or critical) that could fill in the information database to improve the accuracy of physics modeling efforts as the FSP design is refined. Some recommendations for tasks that could be completed in the near term are also included. Specific recommendations on critical test configurations will be reserved until after the sensitivity analyses being conducted by Los Alamos National Laboratory (LANL) are completed (due August 2011).

  11. PULSE COMBUSTOR DESIGN QUALIFICATION TEST AND CLEAN COAL FEEDSTOCK TEST - VOLUME I AND VOLUME II

    SciTech Connect (OSTI)

    Unknown

    2002-02-08

    For this Cooperative Agreement, the pulse heater module is the technology envelope for an indirectly heated steam reformer. The field of use of the steam reformer pursuant to this Cooperative Agreement with DOE is for the processing of sub-bituminous coals and lignite. The main focus is the mild gasification of such coals for the generation of both fuel gas and char--for the steel industry is the main focus. An alternate market application for the substitution of metallurgical coke is also presented. This project was devoted to qualification of a 253-tube pulse heater module. This module was designed, fabricated, installed, instrumented and tested in a fluidized bed test facility. Several test campaigns were conducted. This larger heater is a 3.5 times scale-up of the previous pulse heaters that had 72 tubes each. The smaller heater has been part of previous pilot field testing of the steam reformer at New Bern, North Carolina. The project also included collection and reduction of mild gasification process data from operation of the process development unit (PDU). The operation of the PDU was aimed at conditions required to produce char (and gas) for the Northshore Steel Operations. Northshore Steel supplied the coal for the process unit tests.

  12. Tank 49H salt batch supernate qualification for ARP/MCU

    SciTech Connect (OSTI)

    Nash, C. A.; Peters, T.; Fink, S.; Foster, T.

    2008-08-25

    This report covers the laboratory testing and analyses of Tank 49H Qualification Sample Sets A and C, performed in support of initial radioactive operations of Actinide Removal Process (ARP) and Modular Caustic-Side Solvent Extraction Unit (MCU). Major goals of this work include checking that Tank 49H was well mixed after the last receipt of Tank 23H, characterizing Tank 49H supernate after solids are settled so that its composition can be compared to waste acceptance and hazard criteria, verifying actinide and strontium adsorption with a small scale test using monosodium titanate (MST) and filtration, checking MCU solvent performance when applied to the liquid produced from MST contact, and verifying that in-tank settling after a minimum of 30 days was at least as good or better at reducing solids content after a Tank 49H to Tank 50H transfer occurred than what was observed in less time in the lab. The first four items were covered by Sample Set A. The fifth item was covered by Sample Set C, which had several analyses after compositing as required in the nuclear criticality safety evaluation (NCSE).

  13. SAMPLE RESULTS FROM THE INTEGRATED SALT DISPOSITION PROGRAM MACROBATCH 4 TANK 21H QUALIFICATION SAMPLES

    SciTech Connect (OSTI)

    Peters, T.; Fink, S.

    2011-06-22

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H to qualify them for use in the Integrated Salt Disposition Program (ISDP) Batch 4 processing. All sample results agree with expectations based on prior analyses where available. No issues with the projected Salt Batch 4 strategy are identified. This revision includes additional data points that were not available in the original issue of the document, such as additional plutonium results, the results of the monosodium titanate (MST) sorption test and the extraction, scrub strip (ESS) test. This report covers the revision to the Tank 21H qualification sample results for Macrobatch (Salt Batch) 4 of the Integrated Salt Disposition Program (ISDP). A previous document covers initial characterization which includes results for a number of non-radiological analytes. These results were used to perform aluminum solubility modeling to determine the hydroxide needs for Salt Batch 4 to prevent the precipitation of solids. Sodium hydroxide was then added to Tank 21 and additional samples were pulled for the analyses discussed in this report. This work was specified by Task Technical Request and by Task Technical and Quality Assurance Plan (TTQAP).

  14. SAMPLE RESULTS FROM THE INTERIM SALT DISPOSITION PROGRAM MACROBATCH 8 TANK 21H QUALIFICATION SAMPLES

    SciTech Connect (OSTI)

    Peters, T. B.; Washington, A. L.

    2015-01-13

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 8 for the Interim Salt Disposition Program (ISDP). An Actinide Removal Process (ARP) and several Extraction-Scrub- Strip (ESS) tests were also performed. This document reports characterization data on the samples of Tank 21H as well as simulated performance of ARP and the Modular Caustic Side Solvent Extraction (CSSX) Unit (MCU). No issues with the projected Salt Batch 8 strategy are identified. A demonstration of the monosodium titanate (MST) (0.2 g/L) removal of strontium and actinides provided acceptable average decontamination factors for plutonium of 2.62 (4 hour) and 2.90 (8 hour); and average strontium decontamination factors of 21.7 (4 hour) and 21.3 (8 hour). These values are consistent with results from previous salt batch ARP tests. The two ESS tests also showed acceptable performance with extraction distribution ratios (D{sub (Cs)}) values of 52.5 and 50.4 for the Next Generation Solvent (NGS) blend (from MCU) and NGS (lab prepared), respectively. These values are consistent with results from previous salt batch ESS tests. Even though the performance is acceptable, SRNL recommends that a model for predicting extraction behavior for cesium removal for the blended solvent and NGS be developed in order to improve our predictive capabilities for the ESS tests.

  15. Trial Run of a Junction-Box Attachment Test for Use in Photovoltaic Module Qualification (Presentation)

    SciTech Connect (OSTI)

    Miller, D.; Deibert, S.; Wohlgemuth, J.

    2014-06-01

    Engineering robust adhesion of the junction-box (j-box) is a hurdle typically encountered by photovoltaic (PV) module manufacturers during product development and manufacturing process control. There are historical incidences of adverse effects (e.g., fires), caused when the j-box/adhesive/module system has failed in the field. The addition of a weight to the j-box during the 'damp-heat', 'thermal-cycle', or 'creep' tests within the IEC qualification protocol is proposed to verify the basic robustness of the adhesion system. The details of the proposed test are described, in addition to a trial run of the test procedure. The described experiments examine 4 moisture-cured silicones, 4 foam tapes, and a hot-melt adhesive used in conjunction with glass, KPE, THV, and TPE substrates. For the purpose of validating the experiment, j-boxes were adhered to a substrate, loaded with a prescribed weight, and then subjected to aging. The replicate mock-modules were aged in an environmental chamber (at 85 deg C/85% relative humidity for 1000 hours; then 100 degrees C/<10% relative humidity for 200 hours) or fielded in Golden, Miami, and Phoenix for 1 year. Attachment strength tests, including pluck and shear test geometries, were also performed on smaller component specimens.

  16. Final Scientific EFNUDAT Workshop

    ScienceCinema (OSTI)

    None

    2011-10-06

    The Final Scientific EFNUDAT Workshop - organized by the CERN/EN-STI group on behalf of n_TOF Collaboration - will be held at CERN, Geneva (Switzerland) from 30 August to 2 September 2010 inclusive.EFNUDAT website: http://www.efnudat.euTopics of interest include: Data evaluationCross section measurementsExperimental techniquesUncertainties and covariancesFission propertiesCurrent and future facilities  International Advisory Committee: C. Barreau (CENBG, France)T. Belgya (IKI KFKI, Hungary)E. Gonzalez (CIEMAT, Spain)F. Gunsing (CEA, France)F.-J. Hambsch (IRMM, Belgium)A. Junghans (FZD, Germany)R. Nolte (PTB, Germany)S. Pomp (TSL UU, Sweden) Workshop Organizing Committee: Enrico Chiaveri (Chairman)Marco CalvianiSamuel AndriamonjeEric BerthoumieuxCarlos GuerreroRoberto LositoVasilis Vlachoudis Workshop Assistant: Géraldine Jean

  17. Final Progress Report

    SciTech Connect (OSTI)

    Josef Michl

    2011-10-31

    In this project we have established guidelines for the design on organic chromophores suitable for producing high triplet yields via singlet fission. We have proven their utility by identifying a chromophore of a structural class that had never been examined for singlet fission before, 1,3-diphenylisobenzofuran, and demonstrating in two independent ways that a thin layer of this material produces a triplet yield of 200% within experimental error. We have also designed a second chromophore of a very different type, again of a structural class that had not been examined for singlet fission before, and found that in a thin layer it produces a 70% triplet yield. Finally, we have enhanced the theoretical understanding of the quantum mechanical nature of the singlet fission process.

  18. FINAL/ SCIENTIFIC TECHNICAL REPORT

    SciTech Connect (OSTI)

    McDonald, Henry; Singh, Suminderpal

    2006-08-28

    The overall objective of the Chattanooga fuel cell demonstrations project was to develop and demonstrate a prototype 5-kW grid-parallel, solid oxide fuel cell (SOFC) system that co-produces hydrogen, based on Ion America’s technology. The commercial viability of the 5kW SOFC system was tested by transporting, installing and commissioning the SOFC system at the Alternative Energy Laboratory at the University of Tennessee – Chattanooga. The system also demonstrated the efficiency and the reliability of the system running on natural gas. This project successfully contributed to the achievement of DOE technology validation milestones from the Technology Validation section of the Hydrogen, Fuel Cells and Infrastructure Technologies Program Multi-Year Research, Development and Demonstration Plan. Results of the project can be found in the final technical report.

  19. Final Technical Report

    SciTech Connect (OSTI)

    Alexander Pigarov

    2012-06-05

    This is the final report for the Research Grant DE-FG02-08ER54989 'Edge Plasma Simulations in NSTX and CTF: Synergy of Lithium Coating, Non-Diffusive Anomalous Transport and Drifts'. The UCSD group including: A.Yu. Pigarov (PI), S.I. Krasheninnikov and R.D. Smirnov, was working on modeling of the impact of lithium coatings on edge plasma parameters in NSTX with the multi-species multi-fluid code UEDGE. The work was conducted in the following main areas: (i) improvements of UEDGE model for plasma-lithium interactions, (ii) understanding the physics of low-recycling divertor regime in NSTX caused by lithium pumping, (iii) study of synergistic effects with lithium coatings and non-diffusive ballooning-like cross-field transport, (iv) simulation of experimental multi-diagnostic data on edge plasma with lithium pumping in NSTX via self-consistent modeling of D-Li-C plasma with UEDGE, and (v) working-gas balance analysis. The accomplishments in these areas are given in the corresponding subsections in Section 2. Publications and presentations made under the Grant are listed in Section 3.

  20. Final Technical Report

    SciTech Connect (OSTI)

    Velasco, Mayda [Northwestern University] [Northwestern University

    2013-11-01

    This work is focused on the design and construction of novel beam diagnostic and instrumentation for charged particle accelerators required for the next generation of linear colliders. Our main interest is in non-invasive techniques. The Northwestern group of Velasco has been a member of the CLIC Test Facility 3 (CTF3) collaboration since 2003, and the beam instrumentation work is developed mostly at this facility1. This 4 kW electron beam facility has a 25-170 MeV electron LINAC. CTF3 performed a set of dedicated measurements to finalize the development of our RF-Pickup bunch length detectors. The RF-pickup based on mixers was fully commissioned in 2009 and the RF-pickup based on diodes was finished in time for the 2010-11 data taking. The analysis of all the data taken in by the summer of 2010 was finish in time and presented at the main conference of the year, LINAC 2010 in Japan.

  1. Electrocatalytic hydrocracking. Final report

    SciTech Connect (OSTI)

    Vaart, D.R. van der

    1992-06-01

    This report describes an electrocatalytic method for the chemical addition of hydrogen to a model hydrocarbon compound. In the method, hydrogen formed by water electrolysis at the counter electrode of an electrochemical cell is delivered via conduction through a proton-conducting solid electrolyte. The working electrode of the cell is, at the same time, a hydrocracking catalyst and therefore promotes the reaction of the hydrogen with the hydrocarbon. This process would have clear and distinct advantages over conventional hydroprocessing technologies in that the hydrogen concentration at the catalyst surface could be controlled and maintained by the applied electromotive force. This control would allow operation of the electrocatalytic reactor at ambient pressures instead of the extremely high hydrogen partial pressures required of conventional reactors. In addition, the direct delivery of hydrogen to the catalyst surface should inhibit coke formation and thus prolong the life of the catalyst. Finally, hydrogen utilization efficiencies should be greatly improved since the hydrogen is delivered directly to the reaction site thereby eliminating hydrogen solubility loss in the effluent stream. This report details the demonstration of (a) the ability of a solid electrolyte to perform as a catalyst, (b) the conduction of hydrogen through a solid electrolyte and (c) the simultaneous exploitation of these two properties. Hence, the essential concept of electrocatalytic hydrocracking has been demonstrated. An objective of future work in this area should be to determine whether the hydrocracking or hydrogenation reactions are actually enhanced during the electrocatalytic process when compared to the conventional catalytic process.

  2. Final Report to DOE

    SciTech Connect (OSTI)

    Ismail Gultepe

    2012-05-15

    This final report summarizes the accomplished goals and provide a list of the publications and presentations made during the project. The goals of the project were accomplished through the various publications submitted to Journals and presentations done at the DOE and international meetings and conferences. The 8 journal articles related to the goals of this project were accepted or submitted. The 23 presentations related to goals of the project were presented at the meetings. There were some minor changes regarding to project goals because of issues encountered during the analysis of the data. For example, a total water probe sensor mounted on the Convair-580 that can be used for defining mixed phase conditions and parameterization, had some problems to estimate magnitude of total water mass, and this resulted in issues providing an accurate parameterization for cloud fraction. Variability related aerosol number concentrations and their composition for direct and indirect effects were studied and published. Results were given to explain aerosol and ice microphysical effects on climate change studies. It is suggested that developed parameterizations should consider the variability in aerosol and ice parameters over the Arctic regions.

  3. SLUDGE WASHING AND DEMONSTRATION OF THE DWPF FLOWSHEET IN THE SRNL SHIELDED CELLS FOR SLUDGE BATCH 5 QUALIFICATION

    SciTech Connect (OSTI)

    Pareizs, J; Cj Bannochie, C; Damon Click, D; Dan Lambert, D; Michael Stone, M; Bradley Pickenheim, B; Amanda Billings, A; Ned Bibler, N

    2008-11-10

    Sludge Batch 5 (SB5) is predominantly a combination of H-modified (HM) sludge from Tank 11 that underwent aluminum dissolution in late 2007 to reduce the total mass of sludge solids and aluminum being fed to the Defense Waste Processing Facility (DWPF) and Purex sludge transferred from Tank 7. Following aluminum dissolution, the addition of Tank 7 sludge and excess Pu to Tank 51, Liquid Waste Operations (LWO) provided the Savannah River National Laboratory (SRNL) a 3-L sample of Tank 51 sludge for SB5 qualification. SB5 qualification included washing the sample per LWO plans/projections (including the addition of a Pu/Be stream from H Canyon), DWPF Chemical Process Cell (CPC) simulations, waste glass fabrication (vitrification), and waste glass chemical durability evaluation. This report documents: (1) The washing (addition of water to dilute the sludge supernatant) and concentration (decanting of supernatant) of the Tank 51 qualification sample to adjust sodium content and weight percent insoluble solids to Tank Farm projections. (2) The performance of a DWPF CPC simulation using the washed Tank 51 sample. This includes a Sludge Receipt and Adjustment Tank (SRAT) cycle, where acid is added to the sludge to destroy nitrite and remove mercury, and a Slurry Mix Evaporator (SME) cycle, where glass frit is added to the sludge in preparation for vitrification. The SME cycle also included replication of five canister decontamination additions and concentrations. Processing parameters for the CPC processing were based on work with a non radioactive simulant. (3) Vitrification of a portion of the SME product and Product Consistency Test (PCT) evaluation of the resulting glass. (4) Rheology measurements of the initial slurry samples and samples after each phase of CPC processing. This work is controlled by a Task Technical and Quality Assurance Plan (TTQAP) , and analyses are guided by an Analytical Study Plan. This work is Technical Baseline Research and Development (R&D) for the DWPF.

  4. EA-1637: Final Environmental Assessment

    Broader source: Energy.gov [DOE]

    10 CFR 431 Energy Conservation Program for Commerical and Industrial Equipment: Packaged Terminal Air Conditioner and Packaged Terminal Heat Pump Energy Conservation Standards; Final Rule

  5. Microsoft Word - Argonne Release Final

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    York; Bettis Atomic Power Laboratory in Pennsylvania; and Argonne National Laboratory in Illinois. ANL's final two legacy contact-handled waste shipments, containing a combined...

  6. LIVE_NSB_final.wmv

    ScienceCinema (OSTI)

    None

    2010-09-01

    National Science Bowl finals and awards at the National Building Museum in Washington D.C. Monday 5/3/2010

  7. Final Exam Location and Time

    E-Print Network [OSTI]

    Final Exam Location and Time. Math 162 Fall 2001. Date: Wednesday December 12, 2001. Time: 7:00 pm -9:00 pm. Location: Lambert Fieldhouse ...

  8. Final Exam Location and Time

    E-Print Network [OSTI]

    Final Exam Location and Time. Math 161 Fall 2001. Date: Friday December 14, 2001. Time: 8:00 am -10:00 am. Location: Lambert Fieldhouse ...

  9. Sample Results From The Interim Salt Disposition Program Macrobatch 7 Tank 21H Qualification Samples

    SciTech Connect (OSTI)

    Peters, T. B.; Washington, A. L. II

    2013-08-08

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 7 for the Interim Salt Disposition Program (ISDP). An ARP and several ESS tests were also performed. This document reports characterization data on the samples of Tank 21H as well as simulated performance of ARP/MCU. No issues with the projected Salt Batch 7 strategy are identified, other than the presence of visible quantities of dark colored solids. A demonstration of the monosodium titanate (0.2 g/L) removal of strontium and actinides provided acceptable 4 hour average decontamination factors for Pu and Sr of 3.22 and 18.4, respectively. The Four ESS tests also showed acceptable behavior with distribution ratios (D(Cs)) values of 15.96, 57.1, 58.6, and 65.6 for the MCU, cold blend, hot blend, and Next Generation Solvent (NGS), respectively. The predicted value for the MCU solvent was 13.2. Currently, there are no models that would allow a prediction of extraction behavior for the other three solvents. SRNL recommends that a model for predicting extraction behavior for cesium removal for the blended solvent and NGS be developed. While no outstanding issues were noted, the presence of solids in the samples should be investigated in future work. It is possible that the solids may represent a potential reservoir of material (such as potassium) that could have an impact on MCU performance if they were to dissolve back into the feed solution. This salt batch is intended to be the first batch to be processed through MCU entirely using the new NGS-MCU solvent.

  10. Qualification and Demonstration Program for SSCL Lighting Systems In Park and Highway Applications

    SciTech Connect (OSTI)

    Don Osborne

    2005-06-30

    Meadow River Enterprises, Inc. (MRE) received a DOE cooperative agreement award in March of 2002 to develop Qualification and Demonstration Program for SSCL Lighting Systems in Parks and Highway Applications. (The SSCL lighting technology is the same technology that was developed under a DOE cooperative agreement DE-FC26-99FT40631.) This project spanned a period of 39 months and ended in June of 2005. Participates in the funding of this project included the US Department of Energy, Rahall Transportation Institute, West Virginia State Parks System, and Meadow River Enterprises, Inc. The total program costs totaled $850,000. The federal contribution to the program totaled $150,000 which represented 17.6% of the total costs. The SSCL is a rugged electroluminescent lamp and was designed for outdoor applications. However, since this is a new technology, there have never been any housing or solar packages assemble for its use in these outdoor applications. The purpose of this program was to develop several types of encasements and solar packages, then evaluate their performances over time. At the end of observations, a conclusion would be reached as to the methodology of encasement and solar package requirements. In addition this project was to evaluate the viability of this application for the SSCL product. In addition this project was to evaluate the feasibility of etching the top conductive layer of the SSCL panel to permit only the needed area to be illuminated; this would reduce the power requirements of a sign. All primary development objectives have been achieved.

  11. MTX final report

    SciTech Connect (OSTI)

    Hooper, E.B. [ed.; Allen, S.L.; Brown, M.D.; Byers, J.A.; Casper, T.A.; Cohen, B.I.; Cohen, R.H.; Fenstermacher, M.E.; Foote, J.H.; Hoshino, K. [and others

    1994-01-01

    The MTX experiment was proposed in 1986 to apply high frequency microwaves generated by a free-electron laser (FEL) to electron cyclotron resonance heating (ECRH) in a high field, high density tokamak. As the absorption of microwaves at the electron cyclotron resonance requires high frequencies, the opportunity of applying a free-electron laser has appeal as the device is not limited to frequencies in the microwave or long millimeter wavelength regions, in contrast to many other sources. In addition, the FEL is inherently a high power source of microwaves, which would permit single units of 10 MW or more, optimum for reactors. Finally, it was recognized early in the study of the application of the FEL based on the induction linear accelerator, that the nonlinear effects associated with the intense pulses of microwaves naturally generated would offer several unique opportunities to apply ECRH to current drive, MHD control, and other plasma effects. It was consequently decided to adapt the induction accelerator based FEL to heating and controlling the tokamak, and to conduct experiments on the associated physics. To this end, the Alcator C tokamak was moved from the Massachusetts Institute of Technology (MIT) to the Lawrence Livermore National Laboratory where it was installed in Building 431 and operated from March, 1989, until the conclusion of the experiment in October, 1992. The FEL, based on the ETA-11 accelerator and IMP wiggler was brought into operation by the LLNL Electron Beam Group and power injected into the tokamak during an experimental run in the Fall, 1989. Following an upgrade by the MTX group, a second experimental run was made lasting from the Winter, 1992 through the end of the experiment. Significant contributions to the ECRH experiments were made by the Japan Atomic Energy Research Institute (JAERI).

  12. Final Uranium Leasing Program Programmatic Environmental Impact...

    Energy Savers [EERE]

    Final Uranium Leasing Program Programmatic Environmental Impact Statement (PEIS) Final Uranium Leasing Program Programmatic Environmental Impact Statement (PEIS) Uranium Leasing...

  13. Interim salt disposition program macrobatch 6 tank 21H qualification monosodium titanate and cesium mass transfer tests

    SciTech Connect (OSTI)

    Washington, A. L. II; Peters, T. B.; Fink, S. D.

    2013-02-25

    Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Interim Salt Disposition Program (ISDP) Batch 6 processing. This qualification material was a set of six samples from Tank 21H in October 2012. This sample was used as a real waste demonstration of the Actinide Removal Process (ARP) and the Extraction-Scrub-Strip (ESS) tests process. The Tank 21H sample was contacted with a reduced amount (0.2 g/L) of MST and characterized for strontium and actinide removal at 0 and 8 hour time intervals in this salt batch. {sup 237}Np and {sup 243}Am were both observed to be below detection limits in the source material, and so these results are not reported in this report. The plutonium and uranium samples had decontamination factor (DF) values that were on par or slightly better than we expected from Batch 5. The strontium DF values are slightly lower than expected but still in an acceptable range. The Extraction, Scrub, and Strip (ESS) testing demonstrated cesium removal, stripping and scrubbing within the acceptable range. Overall, the testing indicated that cesium removal is comparable to prior batches at MCU.

  14. DEVELOPMENT QUALIFICATION AND DISPOSAL OF AN ALTERNATIVE IMMOBILIZED LOW-ACTIVITY WASTE FORM AT THE HANFORD SITE

    SciTech Connect (OSTI)

    SAMS TL; EDGE JA; SWANBERG DJ; ROBBINS RA

    2011-01-13

    Demonstrating that a waste form produced by a given immobilization process is chemically and physically durable as well as compliant with disposal facility acceptance criteria is critical to the success of a waste treatment program, and must be pursued in conjunction with the maturation of the waste processing technology. Testing of waste forms produced using differing scales of processing units and classes of feeds (simulants versus actual waste) is the crux of the waste form qualification process. Testing is typically focused on leachability of constituents of concern (COCs), as well as chemical and physical durability of the waste form. A principal challenge regarding testing immobilized low-activity waste (ILAW) forms is the absence of a standard test suite or set of mandatory parameters against which waste forms may be tested, compared, and qualified for acceptance in existing and proposed nuclear waste disposal sites at Hanford and across the Department of Energy (DOE) complex. A coherent and widely applicable compliance strategy to support characterization and disposal of new waste forms is essential to enhance and accelerate the remediation of DOE tank waste. This paper provides a background summary of important entities, regulations, and considerations for nuclear waste form qualification and disposal. Against this backdrop, this paper describes a strategy for meeting and demonstrating compliance with disposal requirements emphasizing the River Protection Project (RPP) Integrated Disposal Facility (IDF) at the Hanford Site and the fluidized bed steam reforming (FBSR) mineralized low-activity waste (LAW) product stream.

  15. Nuclear power plant cable materials : review of qualification and currently available aging data for margin assessments in cable performance.

    SciTech Connect (OSTI)

    Celina, Mathias Christopher; Gillen, Kenneth Todd; Lindgren, Eric Richard

    2013-05-01

    A selective literature review was conducted to assess whether currently available accelerated aging and original qualification data could be used to establish operational margins for the continued use of cable insulation and jacketing materials in nuclear power plant environments. The materials are subject to chemical and physical degradation under extended radiationthermal- oxidative conditions. Of particular interest were the circumstances under which existing aging data could be used to predict whether aged materials should pass loss of coolant accident (LOCA) performance requirements. Original LOCA qualification testing usually involved accelerated aging simulations of the 40-year expected ambient aging conditions followed by a LOCA simulation. The accelerated aging simulations were conducted under rapid accelerated aging conditions that did not account for many of the known limitations in accelerated polymer aging and therefore did not correctly simulate actual aging conditions. These highly accelerated aging conditions resulted in insulation materials with mostlyinert' aging processes as well as jacket materials where oxidative damage dropped quickly away from the air-exposed outside jacket surface. Therefore, for most LOCA performance predictions, testing appears to have relied upon heterogeneous aging behavior with oxidation often limited to the exterior of the cable cross-section - a situation which is not comparable with the nearly homogenous oxidative aging that will occur over decades under low dose rate and low temperature plant conditions. The historical aging conditions are therefore insufficient to determine with reasonable confidence the remaining operational margins for these materials. This does not necessarily imply that the existing 40-year-old materials would fail if LOCA conditions occurred, but rather that unambiguous statements about the current aging state and anticipated LOCA performance cannot be provided based on original qualification testing data alone. The non-availability of conclusive predictions for the aging conditions of 40-year-old cables implies that the same levels of uncertainty will remain for any re-qualification or extended operation of these cables. The highly variable aging behavior of the range of materials employed also implies that simple, standardized aging tests are not sufficient to provide the required aging data and performance predictions for all materials. It is recommended that focused studies be conducted that would yield the material aging parameters needed to predict aging behaviors under low dose, low temperature plant equivalent conditions and that appropriately aged specimens be prepared that would mimic oxidatively-aged 40- to 60- year-old materials for confirmatory LOCA performance testing. This study concludes that it is not sufficient to expose materials to rapid, high radiation and high temperature levels with subsequent LOCA qualification testing in order to predictively quantify safety margins of existing infrastructure with regard to LOCA performance. We need to better understand how cable jacketing and insulation materials have degraded over decades of power plant operation and how this aging history relates to service life prediction and the performance of existing equipment to withstand a LOCA situation.

  16. MA 224 FINAL EXAM INFORMATION The final exam is scheduled ...

    E-Print Network [OSTI]

    Devilyna L Nichols

    2007-11-14

    The final exam is scheduled for Monday, December 10, at 8:00 a.m. in Lambert. Fieldhouse. Seats are assigned and you should receive your assigned seat from

  17. There are n applicants of similar qualification on an interview list. Their salary demands are from a known distribution. Two managers, I and II, will interview them

    E-Print Network [OSTI]

    Chen, Robert W.

    There are n applicants of similar qualification on an interview list. Their salary demands are from the first n \\Gamma 2 applicants and manager I wants to hire applicant n. Even though their salary demands demands less salary than the one hired by manager II does is maximized ? 2. What is the optimal strategy

  18. ELIMINATION OF THE CHARACTERIZATION OF DWPF POUR STREAM SAMPLE AND THE GLASS FABRICATION AND TESTING OF THE DWPF SLUDGE BATCH QUALIFICATION SAMPLE

    SciTech Connect (OSTI)

    Amoroso, J.; Peeler, D.; Edwards, T.

    2012-05-11

    A recommendation to eliminate all characterization of pour stream glass samples and the glass fabrication and Product Consistency Test (PCT) of the sludge batch qualification sample was made by a Six-Sigma team chartered to eliminate non-value-added activities for the Defense Waste Processing Facility (DWPF) sludge batch qualification program and is documented in the report SS-PIP-2006-00030. That recommendation was supported through a technical data review by the Savannah River National Laboratory (SRNL) and is documented in the memorandums SRNL-PSE-2007-00079 and SRNL-PSE-2007-00080. At the time of writing those memorandums, the DWPF was processing sludge-only waste but, has since transitioned to a coupled operation (sludge and salt). The SRNL was recently tasked to perform a similar data review relevant to coupled operations and re-evaluate the previous recommendations. This report evaluates the validity of eliminating the characterization of pour stream glass samples and the glass fabrication and Product Consistency Test (PCT) of the sludge batch qualification samples based on sludge-only and coupled operations. The pour stream sample has confirmed the DWPF's ability to produce an acceptable waste form from Slurry Mix Evaporator (SME) blending and product composition/durability predictions for the previous sixteen years but, ultimately the pour stream analysis has added minimal value to the DWPF's waste qualification strategy. Similarly, the information gained from the glass fabrication and PCT of the sludge batch qualification sample was determined to add minimal value to the waste qualification strategy since that sample is routinely not representative of the waste composition ultimately processed at the DWPF due to blending and salt processing considerations. Moreover, the qualification process has repeatedly confirmed minimal differences in glass behavior from actual radioactive waste to glasses fabricated from simulants or batch chemicals. In contrast, the variability study has significantly added value to the DWPF's qualification strategy. The variability study has evolved to become the primary aspect of the DWPF's compliance strategy as it has been shown to be versatile and capable of adapting to the DWPF's various and diverse waste streams and blending strategies. The variability study, which aims to ensure durability requirements and the PCT and chemical composition correlations are valid for the compositional region to be processed at the DWPF, must continue to be performed. Due to the importance of the variability study and its place in the DWPF's qualification strategy, it will also be discussed in this report. An analysis of historical data and Production Records indicated that the recommendation of the Six Sigma team to eliminate all characterization of pour stream glass samples and the glass fabrication and PCT performed with the qualification glass does not compromise the DWPF's current compliance plan. Furthermore, the DWPF should continue to produce an acceptable waste form following the remaining elements of the Glass Product Control Program; regardless of a sludge-only or coupled operations strategy. If the DWPF does decide to eliminate the characterization of pour stream samples, pour stream samples should continue to be collected for archival reasons, which would allow testing to be performed should any issues arise or new repository test methods be developed.

  19. Danish Energy Authority Final report

    E-Print Network [OSTI]

    1 Danish Energy Authority Final report Kaliningrad Regional District Heating Network 2004 - 2006 2006 #12;Kaliningrad District Heating Network Project 2004 - 2006 2 Table of content The report........................................................................................................... 7 1.4.1 District heating in the Region

  20. Final Report: Axion "Roadmap" Workshop

    SciTech Connect (OSTI)

    Rosenberg, Leslie J

    2013-03-19

    Final report for "Vistas in Axion Physics: A Roadmap for Theoretical and Experimental Axion Physics through 2025", which was held at the University of Washington, INT, from April 23 - 26, 2012.

  1. Reactor physics project final report

    E-Print Network [OSTI]

    Driscoll, Michael J.

    1970-01-01

    This is the final report in an experimental and theoretical program to develop and apply single- and few-element methods for the determination of reactor lattice parameters. The period covered by the report is January 1, ...

  2. The Archetype Condominium Final Report

    E-Print Network [OSTI]

    The Archetype Condominium Final Report December 2012 Alternative Specifications For Achieving Energy Efficiency Performance Targets #12;This document was prepared by Sustainable Buildings Canada Energy Management Inc Brian Tysoe, MCW Consultants Ltd Ian Stahlbrand, Internat Energy Services Canada

  3. Stanford Geothermal Program Final Report

    E-Print Network [OSTI]

    Stanford University

    1 Stanford Geothermal Program Final Report July 1990 - June 1996 Stanford Geothermal Program. THE EFFECTS OF ADSORPTION ON VAPOR-DOMINATED GEOTHERMAL FIELDS.1 1.1 SUMMARY? ..............................................................................................2 1.4 ADSORPTION IN GEOTHERMAL RESERVOIRS ........................................................3

  4. Final Exam for MA 265

    E-Print Network [OSTI]

    The Final Exam For MA 265: Fall 2002. Date: Thursday, December 12, 2002. Time: 3:20 - 5:20 pm. Room: Lambert Fieldhouse, or check the Online Catalog of

  5. Neutronics qualification of the Jules Horowitz reactor fuel by interpretation of the VALMONT experimental program - Transposition of the uncertainties on the reactivity of JHR with JEF2.2 and JEFF3.1.1

    SciTech Connect (OSTI)

    Leray, O.; Hudelot, J. P.; Antony, M.; Doederlein, C.; Santamarina, A.; Bernard, D.; Vaglio-Gaudard, C.

    2011-07-01

    The new European material testing Jules Horowitz Reactor (JHR), currently under construction in Cadarache center (CEA France), will use LEU (20% enrichment in {sup 235}U) fuels (U{sub 3}Si{sub 2} for the start up and UMoAl in the future) which are quite different from the industrial oxide fuel, for which an extensive neutronics qualification database has been established. The HORUS3D/N neutronics calculation scheme, used for the design and safety studies of the JHR, is being developed within the framework of a rigorous verification-validation-qualification methodology. In this framework, the experimental VALMONT (Validation of Aluminium Molybdenum uranium fuel for Neutronics) program has been performed in the MINERVE facility of CEA Cadarache (France), in order to qualify the capability of HORUS3D/N to accurately calculate the reactivity of the JHR reactor. The MINERVE facility using the oscillation technique provides accurate measurements of reactivity effect of samples. The VALMONT program includes oscillations of samples of UAl{sub x}/Al and UMo/Al with enrichments ranging from 0.2% to 20% and Uranium densities from 2.2 to 8 g/cm{sup 3}. The geometry of the samples and the pitch of the experimental lattice ensure maximum representativeness with the neutron spectrum expected for JHR. By comparing the effect of the sample with the one of a known fuel specimen, the reactivity effect can be measured in absolute terms and be compared to computational results. Special attention was paid to the rigorous determination and reduction of the experimental uncertainties. The calculational analysis of the VALMONT results was performed with the French deterministic code APOLLO2. A comparison of the impact of the different calculation methods, data libraries and energy meshes that were tested is presented. The interpretation of the VALMONT experimental program allowed the qualification of JHR fuel UMoAl8 (with an enrichment of 19.75% {sup 235}U) by the Minerve-dedicated interpretation tool: PIMS. The effect of energy meshes and evaluations put forward the JEFF3.1.1/SHEM scheme that leads to a better calculation of the reactivity effect of VALMONT samples. Then, in order to quantify the impact of the uncertainties linked to the basic nuclear data, their propagation from the cross section measurement to the final computational result was analysed in a rigorous way by using a nuclear data re-estimation method based on Gauss-Newton iterations. This study concludes that the prior uncertainties due to nuclear data (uranium, aluminium, beryllium and water) on the reactivity of the Begin Of Cycle (BOC) for the JHR core reach 1217 pcm at 2{sigma}. Now, the uppermost uncertainty on the JHR reactivity is due to aluminium. (authors)

  6. Introduction Final Cooling Channel -High Frequency RF

    E-Print Network [OSTI]

    McDonald, Kirk

    Outline Introduction Final Cooling Channel - High Frequency RF Muon Collider Final Cooling Hisham Sayed February 27, 2014 1 / 10 #12;Outline Introduction Final Cooling Channel - High Frequency RF Table of Contents 1 Introduction 2 Final Cooling Channel - High Frequency RF 2 / 10 #12;Outline Introduction Final

  7. Results from the DOE Advanced Gas Reactor Fuel Development and Qualification Program

    SciTech Connect (OSTI)

    David Petti

    2014-06-01

    Modular HTGR designs were developed to provide natural safety, which prevents core damage under all design basis accidents and presently envisioned severe accidents. The principle that guides their design concepts is to passively maintain core temperatures below fission product release thresholds under all accident scenarios. This level of fuel performance and fission product retention reduces the radioactive source term by many orders of magnitude and allows potential elimination of the need for evacuation and sheltering beyond a small exclusion area. This level, however, is predicated on exceptionally high fuel fabrication quality and performance under normal operation and accident conditions. Germany produced and demonstrated high quality fuel for their pebble bed HTGRs in the 1980s, but no U.S. manufactured fuel had exhibited equivalent performance prior to the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. The design goal of the modular HTGRs is to allow elimination of an exclusion zone and an emergency planning zone outside the plant boundary fence, typically interpreted as being about 400 meters from the reactor. To achieve this, the reactor design concepts require a level of fuel integrity that is better than that claimed for all prior US manufactured TRISO fuel, by a few orders of magnitude. The improved performance level is about a factor of three better than qualified for German TRISO fuel in the 1980’s. At the start of the AGR program, without a reactor design concept selected, the AGR fuel program selected to qualify fuel to an operating envelope that would bound both pebble bed and prismatic options. This resulted in needing a fuel form that could survive at peak fuel temperatures of 1250°C on a time-averaged basis and high burnups in the range of 150 to 200 GWd/MTHM (metric tons of heavy metal) or 16.4 to 21.8% fissions per initial metal atom (FIMA). Although Germany has demonstrated excellent performance of TRISO-coated UO2 particle fuel up to about 10% FIMA and 1150°C, UO2 fuel is known to have limitations because of CO formation and kernel migration at the high burnups, power densities, temperatures, and temperature gradients that may be encountered in the prismatic modular HTGRs. With uranium oxycarbide (UCO) fuel, the kernel composition is engineered to prevent CO formation and kernel migration, which are key threats to fuel integrity at higher burnups, temperatures, and temperature gradients. Furthermore, the recent poor fuel performance of UO2 TRISO fuel pebbles measured in Chinese irradiation testing in Russia and in German pebbles irradiated at 1250°C, and historic data on poorer fuel performance in safety testing of German pebbles that experienced burnups in excess of 10% FIMA [1] have each raised concern about the use of UO2 TRISO above 10% FIMA and 1150°C and the degree of margin available in the fuel system. This continues to be an active area of study internationally.

  8. Technical considerations related to interim source-term assumptions for emergency planning and equipment qualification. [PWR; BWR

    SciTech Connect (OSTI)

    Niemczyk, S.J.; McDowell-Boyer, L.M.

    1982-09-01

    The source terms recommended in the current regulatory guidance for many considerations of light water reactor (LWR) accidents were developed a number of years ago when understandings of many of the phenomena pertinent to source term estimation were relatively primitive. The purpose of the work presented here was to develop more realistic source term assumptions which could be used for interim regulatory purposes for two specific considerations, namely, equipment qualification and emergency planning. The overall approach taken was to adopt assumptions and models previously proposed for various aspects of source term estimation and to modify those assumptions and models to reflect recently gained insights into, and data describing, the release and transport of radionuclides during and after LWR accidents. To obtain illustrative estimates of the magnitudes of the source terms, the results of previous calculations employing the adopted assumptions and models were utilized and were modified to account for the effects of the recent insights and data.

  9. Verification Of The Defense Waste Processing Facility's (DWPF) Process Digestion Methods For The Sludge Batch 8 Qualification Sample

    SciTech Connect (OSTI)

    Click, D. R.; Edwards, T. B.; Wiedenman, B. J.; Brown, L. W.

    2013-03-18

    This report contains the results and comparison of data generated from inductively coupled plasma – atomic emission spectroscopy (ICP-AES) analysis of Aqua Regia (AR), Sodium Peroxide/Sodium Hydroxide Fusion Dissolution (PF) and Cold Chem (CC) method digestions and Cold Vapor Atomic Absorption analysis of Hg digestions from the DWPF Hg digestion method of Sludge Batch 8 (SB8) Sludge Receipt and Adjustment Tank (SRAT) Receipt and SB8 SRAT Product samples. The SB8 SRAT Receipt and SB8 SRAT Product samples were prepared in the SRNL Shielded Cells, and the SRAT Receipt material is representative of the sludge that constitutes the SB8 Batch or qualification composition. This is the sludge in Tank 51 that is to be transferred into Tank 40, which will contain the heel of Sludge Batch 7b (SB7b), to form the SB8 Blend composition.

  10. SLUDGE WASHING AND DEMONSTRATION OF THE DWPF FLOWSHEET IN THE SRNL SHIELDED CELLS FOR SLUDGE BATCH 7A QUALIFICATION

    SciTech Connect (OSTI)

    Pareizs, J.; Billings, A.; Click, D.

    2011-07-08

    Waste Solidification Engineering (WSE) has requested that characterization and a radioactive demonstration of the next batch of sludge slurry (Sludge Batch 7a*) be completed in the Shielded Cells Facility of the Savannah River National Laboratory (SRNL) via a Technical Task Request (TTR). This characterization and demonstration, or sludge batch qualification process, is required prior to transfer of the sludge from Tank 51 to the Defense Waste Processing Facility (DWPF) feed tank (Tank 40). The current WSE practice is to prepare sludge batches in Tank 51 by transferring sludge from other tanks. Discharges of nuclear materials from H Canyon are often added to Tank 51 during sludge batch preparation. The sludge is washed and transferred to Tank 40, the current DWPF feed tank. Prior to transfer of Tank 51 to Tank 40, SRNL simulates the Tank Farm and DWPF processes with a Tank 51 sample (referred to as the qualification sample). Sludge Batch 7a (SB7a) is composed of portions of Tanks 4, 7, and 12; the Sludge Batch 6 heel in Tank 51; and a plutonium stream from H Canyon. SRNL received the Tank 51 qualification sample (sample ID HTF-51-10-125) following sludge additions to Tank 51. This report documents: (1) The washing (addition of water to dilute the sludge supernate) and concentration (decanting of supernate) of the SB7a - Tank 51 qualification sample to adjust sodium content and weight percent insoluble solids to Tank Farm projections. (2) The performance of a DWPF Chemical Process Cell (CPC) simulation using the washed Tank 51 sample. The simulation included a Sludge Receipt and Adjustment Tank (SRAT) cycle, where acid was added to the sludge to destroy nitrite and reduce mercury, and a Slurry Mix Evaporator (SME) cycle, where glass frit was added to the sludge in preparation for vitrification. The SME cycle also included replication of five canister decontamination additions and concentrations. Processing parameters were based on work with a non-radioactive simulant. (3) Vitrification of a portion of the SME product and characterization and durability testing (as measured by the Product Consistency Test (PCT)) of the resulting glass. (4) Rheology measurements of the initial slurry samples and samples after each phase of CPC processing. This program was controlled by a Task Technical and Quality Assurance Plan (TTQAP), and analyses were guided by an Analytical Study Plan. This work is Technical Baseline Research and Development (R&D) for the DWPF. It should be noted that much of the data in this document has been published in interoffice memoranda. The intent of this technical report is bring all of the SB7a related data together in a single permanent record and to discuss the overall aspects of SB7a processing.

  11. AGR-2 Data Qualification Report for ATR Cycles 149B, 150A, 150B, 151A, and 151B

    SciTech Connect (OSTI)

    Michael L. Abbott; Binh T. Pham

    2012-06-01

    This report provides the data qualification status of AGR-2 fuel irradiation experimental data from Advanced Test Reactor (ATR) cycles 149B, 150A, 150B, 151A, and 151B), as recorded in the Nuclear Data Management and Analysis System (NDMAS). The AGR-2 data streams addressed include thermocouple temperatures, sweep gas data (flow rate, pressure, and moisture content), and fission product monitoring system (FPMS) data for each of the six capsules in the experiment. A total of 3,307,500 5-minute thermocouple and sweep gas data records were received and processed by NDMAS for this period. There are no AGR-2 data for cycle 150A because the experiment was removed from the reactor. Of these data, 82.2% were determined to be Qualified based on NDMAS accuracy testing and data validity assessment. There were 450,557 Failed temperature records due to thermocouple failures, and 138,528 Failed gas flow records due to gas flow cross-talk and leakage problems that occurred in the capsules after cycle 150A. For FPMS data, NDMAS received and processed preliminary release rate and release-to-birth rate ratio (R/B) data for the first three reactor cycles (cycles 149B, 150B, and 151B). This data consists of 45,983 release rate records and 45,235 R/B records for the 12 radionuclides reported. The qualification status of these FPMS data has been set to In Process until receipt of QA-approved data generator reports. All of the above data have been processed and tested using a SAS®-based enterprise application software system, stored in a secure Structured Query Language database, and made available on the NDMAS Web portal (http://ndmas.inl.gov) for both internal and external VHTR project participants.

  12. Blackout 2003: Blackout Final Implementation Report | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Report Final Report on the August 14, 2003 Blackout in the United States and Canada: Causes and Recommendations Blackout Final Implementation Report More Documents &...

  13. Ocean Thermal Extractable Energy Visualization: Final Technical...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Ocean Thermal Extractable Energy Visualization: Final Technical Report Ocean Thermal Extractable Energy Visualization: Final Technical Report Report about the Ocean Thermal...

  14. Optimized Fault Location Final Project Report

    E-Print Network [OSTI]

    Optimized Fault Location Final Project Report Power Systems Engineering Research Center A National Engineering Research Center Optimized Fault Location Concurrent Technologies Corporation Final Project Report

  15. Cybersecurity Risk Management Process (RMP) Guideline - Final...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Cybersecurity Risk Management Process (RMP) Guideline - Final (May 2012) Cybersecurity Risk Management Process (RMP) Guideline - Final (May 2012) This electricity subsector...

  16. VARSITY SPORTS Football Fixture List Final

    E-Print Network [OSTI]

    Wagner, Stephan

    VARSITY SPORTS Football Fixture List ­ Final 2015 VARSITY FOOTBALL #12;VARSITY SPORTS Football Fixture List ­ Final 3-Sept 15 28 18

  17. Final Green Zia Award Release

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) | SciTechSubmittedEcologist Final Site-WideDraftFinalGreen

  18. Final Meeting Summary Page 1

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) | SciTechSubmittedEcologist FinalHealth,May 12, 2015 FINAL

  19. CATCHER VESSEL INTERCOOPERATIVE FINAL REPORT

    E-Print Network [OSTI]

    2001 CATCHER VESSEL INTERCOOPERATIVE FINAL REPORT TO THE NORTH PACIFIC FISHERY MANAGEMENT COUNCIL. The Race for Fish 8 Graph 2.2a 1999 & 2001 Mothership Pollock Harvest 9 Graph 2.2b 1999 & 2001 Inshore - Coop Sideboard Caps, Transfers, and Directed Fishing Appendix IX - BBRKC Management Plan #12;3 Section

  20. FINAL REPORT A HIGH SEASONAL

    E-Print Network [OSTI]

    Oak Ridge National Laboratory

    #12;'I MTI 79TR68 FINAL REPORT A HIGH SEASONAL PERFORMANCE FACTOR GAS HEAT PUMP FOR THE NORTH Model Gas Heat Pump ......... 11-4 11.4 CNG Typical Weather Year Selection Method. . . . 11-5 11 of the subject gas-fueled heat pump under development in comparison with other equipment which

  1. MINIMARS conceptual design: Final report

    SciTech Connect (OSTI)

    Lee, J.D.

    1986-09-01

    This volume contains the following sections: (1) fueling systems; (2) blanket; (3) alternative blanket concepts; (4) halo scraper/direct converter system study and final conceptual design; (5) heat-transport and power-conversion systems; (6) tritium systems; (7) minimars air detritiation system; (8) appropriate radiological safety design criteria; and (9) cost estimate. (MOW)

  2. Final Exam Memo/Preparation

    E-Print Network [OSTI]

    odavis

    2010-11-21

    The homework problems listed on the Assignment Sheet for the entire semester is your best guide to ... On the web page you will find a set of practice questions for the final exam. ... The old exams on the webpage are also good to practice.

  3. FINAL REPORT ESTABLISHMENT AND MAINTENANCE

    E-Print Network [OSTI]

    Rathbun, Julie A.

    #12;FINAL REPORT ESTABLISHMENT AND MAINTENANCE OF A MANNED LUNAR BASE IN THE TIME PERIOD 1970. Phase One: Presupply ......... . 1 2. Phase Two: Manned Lunar Landings . 6 3. Phase Three: Logistic Base Class Vehicles ...... . Competing Rendezvous Modes. Concepts: Manned Lunar Landings Logistic Base

  4. Stanford Geothermal Program Final Report

    E-Print Network [OSTI]

    Stanford University

    Stanford Geothermal Program Final Report July 1996 - June 1999 Funded by the U.S. Department of Energy under grant number DE-FG07-95ID13370 Stanford Geothermal Program Department of Petroleum ....................................................................................................................6 2. THE ROLE OF CAPILLARY FORCES IN THE NATURAL STATE OF FRACTURED GEOTHERMAL RESERVOIRS

  5. Danish Energy Authority Final Report

    E-Print Network [OSTI]

    on the energy performance for larger existing buildings subject to major renovation 4. Energy performanceDanish Energy Authority Final Report Implementation of the EU directive on the energy performance of buildings: Development of the Latvian Scheme for energy auditing of buildings and inspection of boilers

  6. Final Draft *** Final Draft *** Final Draft Hanford Advisory Board 2013 Program of Work

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) | SciTechSubmittedEcologist Final Site-WideDraft *** Final

  7. Analysis of tank 4 (FTF-4-15-22, 23) surface and subsurface supernatant samples in support of enrichment control, corrosion control and evaporator feed qualification programs

    SciTech Connect (OSTI)

    Oji, L. N.

    2015-09-09

    This report provides the results of analyses on Savannah River Site Tank 4 surface and subsurface supernatant liquid samples in support of the Enrichment Control Program (ECP), the Corrosion Control Program (CCP) and the Evaporator Feed Qualification (EFQ) Program. The purpose of the ECP sample taken from Tank 4 in August 2015 was to determine if the supernatant liquid would be “acceptable feed” to the 2H and 3H evaporator systems.

  8. Final Flue Gas Cleaning (FFGC) 

    E-Print Network [OSTI]

    Stinger, D. H.; Romero, M. H.

    2006-01-01

    -scale FFGC plant. I. EMISSION REDUCTION TECHNOLOGIES Pollution reduction technologies addressed in this document can be used to clean up any type of flue gas including the high pollution levels from untreated coal fired power plants. A typical... tons by 2010 and at 15 tons by 2018. Although coal fired industry representatives state, “there still is no mercury control technology that exists today that can achieve the reduction levels finalized by the Clean Air Mercury rule”( g ), WOW...

  9. Risk-Informed Safety Margin Characterization Case Study: Selection of Electrical Equipment to Be Subjected to Environmental Qualification

    SciTech Connect (OSTI)

    D. P. Blanchard; R. W. Youngblood

    2014-06-01

    The Risk-Informed Safety Margin Characterization (RISMC) pathway of the DOE’s Light Water Reactor Sustainability (LWRS) program focuses on advancing the state of the art in safety analysis and risk assessment to support decision-making on nuclear power plant operation well beyond the originally designed lifetime of the plants (i.e., beyond 60 years). Among the issues being addressed in RISMC is the significance of SSC aging and how confident we are about our understanding of its impact on the margin between the loads SSCs are expected to see during normal operation and accident conditions, and the SSC capacities (their ability to resist those loads) as the SSCs age. In this paper, a summary is provided of a case study that examines SSC aging from an environmental qualification (EQ) perspective. The case study illustrates how the state of knowledge regarding SSC margin can be characterized given the overall integrated plant design, and was developed to demonstrate a method for deciding on which cables to focus, which cables are not so important from an environmental qualification margin standpoint, and what plant design features or operating characteristics determine the role that environmental qualification plays in establishing a safety case on which decisions regarding margin can be made. The selection of cables for which demonstration of margin with respect to aging and environmental challenges uses a technique known as Prevention Analysis. Prevention Analysis is a Boolean method for optimal selection of SSCs (that is, those combinations of SSCs both necessary and sufficient to meet a predetermined selection criterion) in a manner that allows demonstration that plant-level safety can be demonstrated by the collection of selected SSCs alone. Choosing the set of SSCs that is necessary and sufficient to satisfy the safety objectives, and demonstrating that the safety objectives can be met effectively, determines where resources are best allocated to assure SSC performance margin. The paper describes the resulting component types that were selected by Prevention Analysis and identifies the accident sequence characteristics that cause these component types to be important from an EQ and aging perspective (and, hence, worthwhile evaluating the extent of safety margin). In addition, component types not selected as needing significant margin from an EQ and aging perspective are discussed and an engineering rationale is developed justifying the lack of need to apply resources to demonstrating margin for these component types. This rationale is in terms of design features of the plant and operating characteristics that make these component types less important from an EQ and aging perspective. While the case study focuses on EQ and aging of equipment and cables located inside the containment of this PWR, the prevention analysis method is demonstrated to be an effective technique for identification of minimal collections of components that would be effective in managing safety for a variety of issues associated with aging and long-term operation of the fleet of plants.

  10. Supplemental Immobilization Cast Stone Technology Development and Waste Form Qualification Testing Plan

    SciTech Connect (OSTI)

    Westsik, Joseph H.; Serne, R. Jeffrey; Pierce, Eric M.; Cozzi, Alex; Chung, Chul-Woo; Swanberg, David J.

    2013-05-31

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is being constructed to treat the 56 million gallons of radioactive waste stored in 177 underground tanks at the Hanford Site. The WTP includes a pretreatment facility to separate the wastes into high-level waste (HLW) and low-activity waste (LAW) fractions for vitrification and disposal. The LAW will be converted to glass for final disposal at the Integrated Disposal Facility (IDF). The pretreatment facility will have the capacity to separate all of the tank wastes into the HLW and LAW fractions, and the HLW Vitrification Facility will have the capacity to vitrify all of the HLW. However, a second immobilization facility will be needed for the expected volume of LAW requiring immobilization. A number of alternatives, including Cast Stone—a cementitious waste form—are being considered to provide the additional LAW immobilization capacity.

  11. WP-07 Final Studies & Documentation (wp07/final)

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power AdministrationRobust,Field-effectWorking WithTelecentricN A 035(92/02) nerg *415, 2014OctoberFinal

  12. Qualification of the Savannah River National Laboratories Coulometer, Model SRNL-Rev. 2 (Serial # SRNL-003 Coulometer) for use in Process 3401a, Plutonium Assay by Controlled Coulometer

    SciTech Connect (OSTI)

    Tandon, Lav [Los Alamos National Laboratory; Colletti, Lisa M. [Los Alamos National Laboratory; Drake, Lawrence R. [Los Alamos National Laboratory; Lujan, Elmer J. W. [Los Alamos National Laboratory; Garduno, Katherine [Los Alamos National Laboratory

    2012-08-22

    This report discusses the process used to prove in the SRNL-Rev.2 coulometer for isotopic data analysis used in the special plutonium material project. In May of 2012, the PAR 173 coulometer system that had been the workhorse of the Plutonium Assay team since the early 1970s became inoperable. A new coulometer system had been purchased from Savannah River National Laboratory (SRNL) and installed in August of 2011. Due to funding issues the new system was not qualified at that time. Following the failure of the PAR 173, it became necessary to qualify the new system for use in Process 3401a, Plutonium Assay by Controlled Coulometry. A qualification plan similar to what is described in PQR -141a was followed. Experiments were performed to establish a statistical summary of the performance of the new system by monitoring the repetitive analysis of quality control sample, PEOL, and the assay of plutonium metals obtained from the Plutonium Exchange Program. The data for the experiments was acquired using work instructions ANC125 and ANC195. Figure 1 shows approximately 2 years of data for the PEOL material obtained using the PAR 173. The required acceptance criteria for the sample are that it returns the correct value for the quality control material of 88.00% within 2 sigma (95% Confidence Interval). It also must meet daily precision standards that are set from the historical data analysis of decades of data. The 2 sigma value that is currently used is 0.146 % as evaluated by the Statistical Science Group, CCS-6. The average value of the PEOL quality control material run in 10 separate days on the SRNL-03 coulometer is 87.98% with a relative standard deviation of 0.04 at the 95% Confidence interval. The date of data acquisition is between 5/23/2012 to 8/1/2012. The control samples are run every day experiments using the coulometer are carried out. It is also used to prove an instrument is in statistical control before any experiments are undertaken. The total number of replicate controls run with the new coulometer to date, is n=18. This value is identical to that calculated by the LANL statistical group for this material from data produced by the PAR 173 system over the period of October 2007 to May 2011. The final validation/verification test was to run a blind sample over multiple days. AAC participates in a plutonium exchange program which supplies blind Pu metal samples to the group on a regular basis. The Pu material supplied for this study was ran using the PAR 173 in the past and more recently with the new system. Table 1a contains the values determined through the use of the PAR 173 and Table 1b contains the values obtained with the new system. The Pu assay value obtained on the SRNL system is for paired analysis and had a value of 98.88+/-0.07% RSD at 95% CI. The Pu assay value (decay corrected to July 2012) of the material determined in prior measurements using the PAR173 is 99.05 +/- 0.06 % RSD at 95% CI. We believe that the instrument is adequate to meet the needs of the program.

  13. VERIFICATION OF THE DEFENSE WASTE PROCESSING FACILITY'S (DWPF) PROCESS DIGESTION METHOD FOR THE SLUDGE BATCH 7A QUALIFICATION SAMPLE

    SciTech Connect (OSTI)

    Click, D.; Edwards, T.; Jones, M.; Wiedenman, B.

    2011-03-14

    For each sludge batch that is processed in the Defense Waste Processing Facility (DWPF), the Savannah River National Laboratory (SRNL) performs confirmation of the applicability of the digestion method to be used by the DWPF lab for elemental analysis of Sludge Receipt and Adjustment Tank (SRAT) receipt samples and SRAT product process control samples. DWPF SRAT samples are typically dissolved using a room temperature HF-HNO{sub 3} acid dissolution (i.e., DWPF Cold Chem Method, see DWPF Procedure SW4-15.201) and then analyzed by inductively coupled plasma - atomic emission spectroscopy (ICP-AES). This report contains the results and comparison of data generated from performing the Aqua Regia (AR), Sodium peroxide/Hydroxide Fusion (PF) and DWPF Cold Chem (CC) method digestions of Sludge Batch 7a (SB7a) SRAT Receipt and SB7a SRAT Product samples. The SB7a SRAT Receipt and SB7a SRAT Product samples were prepared in the SRNL Shielded Cells, and the SRAT Receipt material is representative of the sludge that constituates the SB7a Batch or qualification composition. This is the sludge in Tank 51 that is to be transferred into Tank 40, which will contain the heel of Sludge Batch 6 (SB6), to form the Sb7a Blend composition.

  14. Trial-Run of a Junction-Box Attachment Test for Use in Photovoltaic Module Qualification: Preprint

    SciTech Connect (OSTI)

    Miller, D. C.; Deibert, S. L.; Wohlgemuth, J. H.

    2014-06-01

    Engineering robust adhesion of the junction box (j-box) is a hurdle typically encountered by photovoltaic module manufacturers during product development and manufacturing process control. There are historical incidences of adverse effects (e.g., fires) caused when the j-box/adhesive/module system has failed in the field. The addition of a weight to the j-box during the 'damp-heat,' 'thermal-cycle,' or 'creep' tests within the IEC qualification protocol is proposed to verify the basic robustness of the adhesion system. The details of the proposed test are described, in addition to a trial-run of the test procedure. The described experiments examine four moisture-cured silicones, four foam tapes, and a hot-melt adhesive used in conjunction with glass, KPE, THV, and TPE substrates. For the purpose of validating the experiment, j-boxes were adhered to a substrate, loaded with a prescribed weight, and then subjected to aging. The replicate mock-modules were aged in an environmental chamber (at 85 degrees C/85% relative humidity for 1000 hours; then 100 degrees C/<10% relative humidity for 200 hours) or fielded in Golden (CO), Miami (FL), and Phoenix (AZ) for one year. Attachment strength tests, including pluck and shear test geometries, were also performed on smaller component specimens.

  15. Virtualized Network Control. Final Report

    SciTech Connect (OSTI)

    Ghani, Nasir

    2013-02-01

    This document is the final report for the Virtualized Network Control (VNC) project, which was funded by the United States Department of Energy (DOE) Office of Science. This project was also informally referred to as Advanced Resource Computation for Hybrid Service and TOpology NEtworks (ARCHSTONE). This report provides a summary of the project's activities, tasks, deliverable, and accomplishments. It also provides a summary of the documents, software, and presentations generated as part of this projects activities. Namely, the Appendix contains an archive of the deliverables, documents, and presentations generated a part of this project.

  16. [Experimental nuclear physics]. Final report

    SciTech Connect (OSTI)

    NONE

    1991-04-01

    This is the final report of the Nuclear Physics Laboratory of the University of Washington on work supported in part by US Department of Energy contract DE-AC06-81ER40048. It contains chapters on giant dipole resonances in excited nuclei, nucleus-nucleus reactions, astrophysics, polarization in nuclear reactions, fundamental symmetries and interactions, accelerator mass spectrometry (AMS), ultra-relativistic heavy ions, medium energy reactions, work by external users, instrumentation, accelerators and ion sources, and computer systems. An appendix lists Laboratory personnel, a Ph. D. degree granted in the 1990-1991 academic year, and publications. Refs., 41 figs., 7 tabs.

  17. New Approaches to Final Cooling

    E-Print Network [OSTI]

    Neuffer, David

    2015-01-01

    A high-energy muon collider scenario requires a "final cooling" system that reduces transverse emittance by a factor of ~10 while allowing longitudinal emittance increase. The baseline approach has low-energy transverse cooling within high-field solenoids, with strong longitudinal heating. This approach and its recent simulation are discussed. Alternative approaches which more explicitly include emittance exchange are also presented. Round-to-flat beam transform, transverse slicing, and longitudinal bunch coalescence are possible components of the alternative approach. A more explicit understanding of solenoidal cooling beam dynamics is introduced.

  18. FINAL TECHNICAL REPORT-DJ

    Office of Scientific and Technical Information (OSTI)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield MunicipalTechnical Report:Speeding accessby aLED Street Lighting FINAL TECHNICAL REPORT Project

  19. UM-ASU Final Report

    Office of Scientific and Technical Information (OSTI)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield MunicipalTechnicalInformation4563 LLNL Small-scale Friction Sensitivity (BAM) Test . *UM-ASU Final

  20. Final Meeting Summary Page 1

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    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) | SciTechSubmittedEcologist FinalHealth, Safety, and

  1. Final Meeting Summary Page 1

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    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) | SciTechSubmittedEcologist FinalHealth, Safety, andRiver

  2. Final Meeting Summary Page 1

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  3. Final Meeting Summary Page 1

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    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) | SciTechSubmittedEcologist FinalHealth, Safety,

  4. Final Meeting Summary Page 1

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    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) | SciTechSubmittedEcologist FinalHealth, Safety, November

  5. Final Meeting Summary Page 1

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    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) | SciTechSubmittedEcologist FinalHealth, Safety,

  6. Final Meeting Summary Page 1

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    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) | SciTechSubmittedEcologist FinalHealth, Safety,7, 2015

  7. Final Meeting Summary Page 1

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    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) | SciTechSubmittedEcologist FinalHealth, Safety,7, 20151,

  8. Final Meeting Summary Page 1

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    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) | SciTechSubmittedEcologist FinalHealth, Safety,7,

  9. Final Meeting Summary Page 1

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    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) | SciTechSubmittedEcologist FinalHealth, Safety,7,March 11,

  10. Final Meeting Summary Page 1

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    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) | SciTechSubmittedEcologist FinalHealth, Safety,7,March

  11. Final Meeting Summary Page 1

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    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) | SciTechSubmittedEcologist FinalHealth,

  12. Final Meeting Summary Page 1

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    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) | SciTechSubmittedEcologist FinalHealth,May 12, 2015

  13. Final Meeting Summary Page 1

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    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) | SciTechSubmittedEcologist FinalHealth,May 12, 2015August

  14. Final Meeting Summary Page 1

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    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) | SciTechSubmittedEcologist FinalHealth,May 12,

  15. Final Meeting Summary Page 1

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    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) | SciTechSubmittedEcologist FinalHealth,May 12,Health,

  16. Final Meeting Summary Page 1

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    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) | SciTechSubmittedEcologist FinalHealth,May

  17. Final Meeting Summary Page 1

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  18. Final Meeting Summary Page 1

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  19. Final Meeting Summary Page 1

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  20. Final Meeting Summary Page 1

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  1. Final Meeting Summary Page 1

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    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) | SciTechSubmittedEcologist FinalHealth,MayOctoberSeptember

  2. Final Meeting Summary Page 1

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    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) | SciTechSubmittedEcologistand Communication7, 2014 FINAL

  3. Final Meeting Summary Page 1

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    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) | SciTechSubmittedEcologistand9, 2013 FINAL MEETING SUMMARY

  4. Final Meeting Summary Page 1

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) | SciTechSubmittedEcologistand9, 2013 FINAL MEETING

  5. Final Meeting Summary Page 1

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) | SciTechSubmittedEcologistand9, 2013 FINAL MEETINGNovember

  6. Final Meeting Summary Page 1

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) | SciTechSubmittedEcologistand9, 2013 FINAL

  7. FinalProgramReportfinal.doc

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) |Final Report Document Number(Technical FinaldecisionsBES

  8. FRESAR ReleaseFINAL.PDF

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would like submitKansasCommunitiesofExtrans - PermeationGovernmentCOOLING29,FNAL841 138Final

  9. Setting-less Protection Final Project Report

    E-Print Network [OSTI]

    Setting-less Protection Final Project Report Power Systems Engineering Research Center Empowering Minds to Engineer the Future Electric Energy System #12;#12;Setting-less Protection Final Project Report

  10. GDB - Human Genome Database final report

    SciTech Connect (OSTI)

    Talbot, C. Conover, Jr.

    2002-01-08

    This is the DOE final report for the GDB, Human Genome Database, project at the Johns Hopkins University.

  11. Low Frequency Transmission Final Project Report

    E-Print Network [OSTI]

    Low Frequency Transmission Final Project Report Power Systems Engineering Research Center Empowering Minds to Engineer the Future Electric Energy System #12;Low Frequency Transmission Final Project This is the final report for the Power Systems Engineering Research Center (PSERC) research project S-42 titled "Low

  12. Final Year Project Report Supervisor: Dr. MWMak

    E-Print Network [OSTI]

    Mak, Man-Wai

    98/99 Final Year Project Report Supervisor: Dr. MWMak Co­examiner: Dr. Vincent Ng Student: Kwok Kin #12; 98/99 Final Year Project Report Internet Phone Abstract This project is to develop a software. #12; 98/99 Final Year Project Report Internet Phone Acknowledgments While I retrospect the time

  13. Fort Polk EEAP. Final report

    SciTech Connect (OSTI)

    Busch, R.D.; Scheuch, K.E.; Shishman, T.T.

    1986-07-17

    This Final Presentation provides a summary of the work done under Increments A, B, E, and G of the Energy Engineering Analysis Program (EEAP) for Fort Polk Louisiana. The work was accomplished under Contract DACA63-80-C-0166 plus modifications with the Fort Worth District, Corps of Engineers. The vast majority of consumed energy at Fort Polk consists of electricity and natural gas. In FY75, Fort Polk used 48,399,000 kWh of electricity at a cost of $600,000. During that same period, 782,637 MCF of natural gas was purchased for $484,000. The total FY75 energy use was 1,368,327 MBtu.

  14. CHM-6315 (Hiver 2011) TRAVAIL PR-EXAMEN FINAL / PRE-FINAL EXAM ASSIGNMENT

    E-Print Network [OSTI]

    Charette, André

    1/1 CHM-6315 (Hiver 2011) TRAVAIL PRÉ-EXAMEN FINAL / PRE-FINAL EXAM ASSIGNMENT Date de remise in with your final exam. VERSION FRANÇAISE Le but de ce devoir est de préparer un « aide-mémoire » qui résume bien vous préparer ŕ l'examen final. Si vous respectez les consignes, vous ętes garanti d'accumuler 10

  15. SLUDGE WASHING AND DEMONSTRATION OF THE DWPF FLOWSHEET IN THE SRNL SHIELDED CELLS FOR SLUDGE BATCH 6 QUALIFICATION

    SciTech Connect (OSTI)

    Pareizs, J.; Pickenheim, B.; Bannochie, C.; Billings, A.; Bibler, N.; Click, D.

    2010-10-01

    Prior to initiating a new sludge batch in the Defense Waste Processing Facility (DWPF), Savannah River National Laboratory (SRNL) is required to simulate this processing, including Chemical Process Cell (CPC) simulation, waste glass fabrication, and chemical durability testing. This report documents this simulation for the next sludge batch, Sludge Batch 6 (SB6). SB6 consists of Tank 12 material that has been transferred to Tank 51 and subjected to Low Temperature Aluminum Dissolution (LTAD), Tank 4 sludge, and H-Canyon Pu solutions. Following LTAD and the Tank 4 addition, Liquid Waste Operations (LWO) provided SRNL a 3 L sample of Tank 51 sludge for SB6 qualification. Pu solution from H Canyon was also received. SB6 qualification included washing the sample per LWO plans/projections (including the addition of Pu from H Canyon), DWPF CPC simulations, waste glass fabrication (vitrification), and waste glass characterization and chemical durability evaluation. The following are significant observations from this demonstration. Sludge settling improved slightly as the sludge was washed. SRNL recommended (and the Tank Farm implemented) one less wash based on evaluations of Tank 40 heel projections and projections of the glass composition following transfer of Tank 51 to Tank 40. Thorium was detected in significant quantities (>0.1 wt % of total solids) in the sludge. In past sludge batches, thorium has been determined by Inductively Coupled Plasma-Mass Spectroscopy (ICP-MS), seen in small quantities, and reported with the radionuclides. As a result of the high thorium, SRNL-AD has added thorium to their suite of Inductively Coupled Plasma-Atomic Emission Spectroscopy (ICP-AES) elements. The acid stoichiometry for the DWPF Sludge Receipt and Adjustment Tank (SRAT) processing of 115%, or 1.3 mol acid per liter of SRAT receipt slurry, was adequate to accomplish some of the goals of SRAT processing: nitrite was destroyed to below 1,000 mg/kg and mercury was removed to below the DWPF target with 750 g of steam per g of mercury. However, rheological properties did not improve and were above the design basis. Hydrogen generation rates did not exceed DWPF limits during the SRAT and Slurry Mix Evaporator (SME) cycles. However, hydrogen generation during the SRAT cycle approached the DWPF limit. The glass fabricated with the Tank 51 SB6 SME product and Frit 418 was acceptable with respect to chemical durability as measured by the Product Consistency Test (PCT). The PCT response was also predictable by the current durability models of the DWPF Product Composition Control System (PCCS). It should be noted, however, that in the first attempt to make glass from the SME product, the contents of the fabrication crucible foamed over. This may be a result of the SME product's REDOX (Reduction/Oxidation - Fe{sup 2+}/{Sigma}Fe) of 0.08 (calculated from SME product analytical results). The following are recommendations drawn from this demonstration. In this demonstration, at the request of DWPF, SRNL caustic boiled the SRAT contents prior to acid addition to remove water (to increase solids concentration). During the nearly five hours of caustic boiling, 700 ppm of antifoam was required to control foaming. SRNL recommends that DWPF not caustic boil/concentrate SRAT receipt prior to acid addition until further studies can be performed to provide a better foaming control strategy or a new antifoam is developed for caustic boiling. Based on this set of runs and a recently completed demonstration with the SB6 Waste Acceptance Product Specifications (WAPS) sample, it is recommended that DWPF not add formic acid at the design addition rate of two gallons per minute for this sludge batch. A longer acid addition time appears to be helpful in allowing slower reaction of formic acid with the sludge and possibly decreases the chance of a foam over during acid addition.

  16. Advanced Design Studies. Final report

    SciTech Connect (OSTI)

    Steiner, Don [Rensselaer Polytechnic Institute, Troy, NY (United States)

    2012-12-01

    The ARIES-CS project was a multi-year multi-institutional project to assess the feasibility of a compact stellarator as a fusion power plant. The work herein describes efforts to help design one aspect of the device, the divertor, which is responsible for the removal of particle and heat flux from the system, acting as the first point of contact between the magnetically confined hot plasma and the outside world. Specifically, its location and topology are explored, extending previous work on the sub ject. An optimized design is determined for the thermal particle flux using a suite of 3D stellarator design codes which trace magnetic field lines from just inside the confined plasma edge to their strike points on divertor plates. These divertor plates are specified with a newly developed plate design code. It is found that a satisfactory thermal design exists which maintains the plate temperature and heat load distribution below tolerable engineering limits. The design is unique, including a toroidal taper on the outboard plates which was found to be important to our results. The maximum thermal heat flux for the final design was 3.61 M W/m2 and the maximum peaking factor was 10.3, below prescribed limits of 10 M W/m2 and 15.6, respectively. The median length of field lines reaching the plates is about 250 m and their average angle of inclination to the surface is 2 deg. Finally, an analysis of the fast alphas, resulting from fusion in the core, which escape the plasma was performed. A method is developed for obtaining the mapping from magnetic coordinates to real-space coordinates for the ARIES-CS. This allows the alpha exit locations to be identified in real space for the first time. These were then traced using the field line algorithm as well as a guiding center routine accounting for their mass, charge, and specific direction and energy. Results show that the current design is inadequate for accommodating the alpha heat flux, capturing at most 1/3 of lost alphas. However the distribution of the alphas on the device first wall indicates that a viable solution likely exists. It is noted that future designs must be sought which specifically address the fusion alphas through an integrated approach involving physics and engineering teams.

  17. IRIS Final Technical Progress Report

    SciTech Connect (OSTI)

    M. D. Carelli

    2003-11-03

    OAK-B135 This NERI project, originally started as the Secure Transportable Autonomous Light Water Reactor (STAR-LW) and currently known as the International Reactor Innovative and Secure (IRIS) project, had the objective of investigating a novel type of water-cooled reactor to satisfy the Generation IV goals: fuel cycle sustainability, enhanced reliability and safety, and improved economics. The research objectives over the three-year (1999-2002) program were as follows: First year: Assess various design alternatives and establish main characteristics of a point design; Second year: Perform feasibility and engineering assessment of the selected design solutions; Third year: Complete reactor design and performance evaluation, including cost assessment These objectives were fully attained and actually they served to launch IRIS as a full fledged project for eventual commercial deployment. The program did not terminate in 2002 at the end of the NERI program, and has just entered in its fifth year. This has been made possible by the IRIS project participants which have grown from the original four member, two-countries team to the current twenty members, nine countries consortium. All the consortium members work under their own funding and it is estimated that the value of their in-kind contributions over the life of the project has been of the order of $30M. Currently, approximately 100 people worldwide are involved in the project. A very important constituency of the IRIS project is the academia: 7 universities from four countries are members of the consortium and five more US universities are associated via parallel NERI programs. To date, 97 students have worked or are working on IRIS; 59 IRIS-related graduate theses have been prepared or are in preparation, and 41 of these students have already graduated with M.S. (33) or Ph.D. (8) degrees. This ''final'' report (final only as far as the NERI program is concerned) summarizes the work performed in the first four years of IRIS, from October 1999 to October 2003. It provides a panoramic of the project status and design effort, with emphasis on the current status, since two previous reports have very extensively documented the work performed, from inception to early 2002.

  18. Final Guidance for EPAct 2005 Section 242 Hydroelectric Incentive...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Final Guidance for EPAct 2005 Section 242 Hydroelectric Incentive Program Final Guidance for EPAct 2005 Section 242 Hydroelectric Incentive Program This document contains the Final...

  19. The final technical report of the CRADA, Medical Accelerator Technology

    E-Print Network [OSTI]

    Chu, William T.; Rawls, John M.

    2000-01-01

    the marketplace. Final Technical Report: Medical AcceleratorPTCOG XXV, 1996. Final Technical Report: Medical AcceleratorFinal Technical Report: Medical Accelerator Technology (SC-

  20. SRC-I Demonstration Plant Analytical Laboratory. Final technical report

    SciTech Connect (OSTI)

    Hamilton, R.F.; Klusaritz, M.; Maroulis, P.J.; Moyer, J.D.; Parees, D.M.; Skinner, R.W.; Sydlik, E.; Tewari, K.C.; Tiedge, W.F.; Znaimer, S.

    1983-09-01

    This report describes planning and methods development activities to establish an SRC-I Coal Liquefaction Demonstration Plant analytical laboratory. Laboratory requirements are listed and methods qualification/development activities are described for the following areas: microanalytical carbon, hydrogen, chlorine, nitrogen, and sulfur procedures; ash determination; GC/MS and GC/FID analyses; metals analyses; and GC-simulated distillation. 2 references, 64 figures, 108 tables.

  1. Hawaii Clean Energy Final PEIS Summary

    Broader source: Energy.gov (indexed) [DOE]

    HAWAI'I CLEAN ENERGY FINAL PROGRAMMATIC ENVIRONMENTAL IMPACT STATEMENT SUMMARY U.S. DEPARTMENT OF ENERGY Office of Electricity Delivery and Energy Reliability Office of Energy...

  2. Community Power Works Final Report and Conclusions

    SciTech Connect (OSTI)

    Baumel, Christie

    2015-03-09

    This is the final technical report for the City of Seattle's Community Power Works program, funded through the US DOE Better Buildings grant program.

  3. EIS-0408: Final Programmatic Environmental Impact Statement ...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Wind Energy Final Programmatic EIS, which evaluates issues and potential environmental impacts associated with wind energy development within Western's Upper Great Plains...

  4. Energy Department Finalizes Loan Guarantee for Transformational...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    for Transformational Rooftop Solar Project Energy Department Finalizes Loan Guarantee for Transformational Rooftop Solar Project September 30, 2011 - 3:37pm Addthis Washington D.C....

  5. Final Technical Report on Radioxenon Event Analysis

    SciTech Connect (OSTI)

    Ely, James H.; Cooper, Matthew W.; Hayes, James C.; Heimbigner, Tom R.; McIntyre, Justin I.; Schrom, Brian T.

    2013-03-15

    This is a final deliverable report for the Advanced Spectral Analysis for Radioxenon project with a focus on radioxenon event categorization.

  6. EIS-0251: Final Environmental Impact Statement

    Office of Energy Efficiency and Renewable Energy (EERE)

    Department of the Navy Final Environmental Impact Statement for a Container System for the Management of Naval Spent Nuclear Fuel (November 1996)

  7. The Magellan Final Report on Cloud Computing

    E-Print Network [OSTI]

    Coghlan, Susan

    2013-01-01

    Networking Initiative (ANI). Magellan provided storage andNetworking Initiative (ANI) research projects to support2011. Finally, support for ANI research projects started in

  8. Battelle Columbus Laboratories Director's Final Findings and...

    Office of Environmental Management (EM)

    Name Battelle Columbus Laboratories Director's Final Findings and Orders, October 4, 1995 State Ohio Agreement Type Federal Facility Agreement Legal Driver(s) FFCAct Scope...

  9. Portsmouth Gaseous Diffusion Plant Director's Final Findings...

    Office of Environmental Management (EM)

    Portsmouth Gaseous Diffusion Plant Director's Final Findings and Orders, October 4, 1995 State Ohio Agreement Type Federal Facility Agreement Legal Driver(s) FFCAct Scope Summary...

  10. HANFORD THYROID DISEASE STUDY FINAL REPORT

    E-Print Network [OSTI]

    HANFORD THYROID DISEASE STUDY FINAL REPORT Study Management Team Scott Davis, Ph.D., Principal Gilman, Jennifer Sporleder, Jan Kikuchi, Bill Mullin, Liza Noonan, Chuck Wiggins, Belen Gallardo

  11. Clark Public Utilities Impact Evaluation Final Report

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Clark Public Utilities Impact Evaluation Final Report - July 2015 - Home Energy Reports Memorandum 1375 Walnut Street Suite 200 Boulder, CO 80302 303-728-2500 To: Lauren Gage...

  12. OPTIMIZAO E ALGORITMOS Exame final -1 Data

    E-Print Network [OSTI]

    Instituto de Sistemas e Robotica

    OPTIMIZA��O E ALGORITMOS Exame final - 1ª Data 26 de Janeiro de 2004 Nº Nome Classificação 42498

  13. Future Directions in Spatial Demography, Final Report

    E-Print Network [OSTI]

    Matthews, Stephen A.; Janelle, Donald G.; Goodchild, Michael F.

    2012-01-01

    the meeting’s final reception. Future Directions in SpatialH. (2007) Five Minds for the Future. Cambridge, MA: Harvardhorizons, envisioning the future. Social Science and

  14. Final Uranium Leasing Program Programmatic Environmental Impact...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Tribe 11 12 Title: Final Uranium Leasing Program Programmatic Environmental Impact Statement 13 (DOEEIS-0472) 14 15 For additional information on this Programmatic...

  15. Final Conservation Billing Credit Policy Supplement Background...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    December 17, 2014 Page 1 Final Conservation Billing Credit Policy Supplement Background and Need: This Conservation Billing Credit Policy Supplement describes how Bonneville Power...

  16. Bureau of Land Management - Final Programmatic Environmental...

    Open Energy Info (EERE)

    Bureau of Land Management - Final Programmatic Environmental Impact Statement for Geothermal Leasing in the Western United States Jump to: navigation, search OpenEI Reference...

  17. AGR-1 Irradiation Test Final As-Run Report

    SciTech Connect (OSTI)

    Blaise P. Collin

    2012-06-01

    This document presents the as-run analysis of the AGR-1 irradiation experiment. AGR-1 is the first of eight planned irradiations for the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. Funding for this program is provided by the US Department of Energy (DOE) as part of the Next-Generation Nuclear Plant (NGNP) project. The objectives of the AGR-1 experiment are: 1. To gain experience with multi-capsule test train design, fabrication, and operation with the intent to reduce the probability of capsule or test train failure in subsequent irradiation tests. 2. To irradiate fuel produced in conjunction with the AGR fuel process development effort. 3. To provide data that will support the development of an understanding of the relationship between fuel fabrication processes, fuel product properties, and irradiation performance. In order to achieve the test objectives, the AGR-1 experiment was irradiated in the B-10 position of the Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL) for a total duration of 620 effective full power days of irradiation. Irradiation began on December 24, 2006 and ended on November 6, 2009 spanning 13 ATR cycles and approximately three calendar years. The test contained six independently controlled and monitored capsules. Each capsule contained 12 compacts of a single type, or variant, of the AGR coated fuel. No fuel particles failed during the AGR-1 irradiation. Final burnup values on a per compact basis ranged from 11.5 to 19.6 %FIMA, while fast fluence values ranged from 2.21 to 4.39 ?1025 n/m2 (E >0.18 MeV). We’ll say something here about temperatures once thermal recalc is done. Thermocouples performed well, failing at a lower rate than expected. At the end of the irradiation, nine of the originally-planned 19 TCs were considered functional. Fission product release-to-birth (R/B) ratios were quite low. In most capsules, R/B values at the end of the irradiation were at or below 10-7 with only one capsule significantly exceeding this value. A maximum R/B of around 2?10-7 was reached at the end of the irradiation in Capsule 5. Several shakedown issues were encountered and resolved during the first three cycles. These include the repair of minor gas line leaks; repair of faulty gas line valves; the need to position moisture monitors in regions of low radiation fields for proper functioning; the enforcement of proper on-line data storage and backup, the need to monitor thermocouple performance, correcting for detector spectral gain shift, and a change in the mass flow rate range of the neon flow controllers.

  18. AGR-2 IRRADIATION TEST FINAL AS-RUN REPORT

    SciTech Connect (OSTI)

    Blaise, Collin

    2014-07-01

    This document presents the as-run analysis of the AGR-2 irradiation experiment. AGR-2 is the second of the planned irradiations for the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. Funding for this program is provided by the U.S. Department of Energy as part of the Very High Temperature Reactor (VHTR) Technical Development Office (TDO) program. The objectives of the AGR-2 experiment are to: (a) Irradiate UCO (uranium oxycarbide) and UO2 (uranium dioxide) fuel produced in a large coater. Fuel attributes are based on results obtained from the AGR-1 test and other project activities. (b) Provide irradiated fuel samples for post-irradiation experiment (PIE) and safety testing. (c) Support the development of an understanding of the relationship between fuel fabrication processes, fuel product properties, and irradiation performance. The primary objective of the test was to irradiate both UCO and UO2 TRISO (tri-structural isotropic) fuel produced from prototypic scale equipment to obtain normal operation and accident condition fuel performance data. The UCO compacts were subjected to a range of burnups and temperatures typical of anticipated prismatic reactor service conditions in three capsules. The test train also includes compacts containing UO2 particles produced independently by the United States, South Africa, and France in three separate capsules. The range of burnups and temperatures in these capsules were typical of anticipated pebble bed reactor service conditions. The results discussed in this report pertain only to U.S. produced fuel. In order to achieve the test objectives, the AGR-2 experiment was irradiated in the B-12 position of the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) for a total irradiation duration of 559.2 effective full power days (EFPD). Irradiation began on June 22, 2010, and ended on October 16, 2013, spanning 12 ATR power cycles and approximately three and a half calendar years. The test contained six independently controlled and monitored capsules. Each U.S. capsule contained 12 compacts of either UCO or UO2 AGR coated fuel. No fuel particles failed during the AGR-2 irradiation. Final burnup values on a per compact basis ranged from 7.26 to 13.15% FIMA (fissions per initial heavy-metal atom) for UCO fuel, and 9.01 to 10.69% FIMA for UO2 fuel, while fast fluence values ranged from 1.94 to 3.47´1025 n/m2 (E >0.18 MeV) for UCO fuel, and from 3.05 to 3.53´1025 n/m2 (E >0.18 MeV) for UO2 fuel. Time-average volume-average (TAVA) temperatures on a capsule basis at the end of irradiation ranged from 987°C in Capsule 6 to 1296°C in Capsule 2 for UCO, and from 996 to 1062°C in UO2-fueled Capsule 3. By the end of the irradiation, all of the installed thermocouples (TCs) had failed. Fission product release-to-birth (R/B) ratios were quite low. In the UCO capsules, R/B values during the first three cycles were below 10-6 with the exception of the hotter Capsule 2, in which the R/Bs reached 2´10-6. In the UO2 capsule (Capsule 3), the R/B values during the first three cycles were below 10-7. R/B values for all following cycles are not reliable due to gas flow and cross talk issues.

  19. Qualification of JEFF3.1.1 library for high conversion reactor calculations using the ERASME/R experiment

    SciTech Connect (OSTI)

    Vidal, J. F.; Noguere, G.; Peneliau, Y.; Santamarina, A.

    2012-07-01

    With its low CO{sub 2} production, Nuclear Energy appears to be an efficient solution to the global warming due to green-house effect. However, current LWR reactors are poor uranium users and, pending the development of Fast Neutron Reactors, alternative concepts of PWR with higher conversion ratio (HCPWR) are being studied again at CEA, first studies dating from the middle 80's. In these French designs, low moderation ratio has been performed by tightening the lattice pitch, achieving a conversion ratio of 0.8-0.9 with a MOX fuel coming from PWR UOX recycling. Theses HCPWRs are characterized by a harder neutron spectrum and the calculation uncertainties on the fundamental neutronics parameters are increased by a factor 3 regarding a standard PWR lattice, due to the major contribution of the Plutonium isotopes and of the epithermal energy range to the reaction rates. In order to reduce these uncertainties, a 3-year experimental validation program called ERASME has been performed by CEA from 1984 to 1986 in the EOLE reactor. Monte Carlo analysis of the ERASME/R experiments with the Monte Carlo code TRIPOLI4 allowed the qualification of the recommended JEFF.3.1.1 library for major neutronics parameters. K{sub eff} of the MOX under-moderated lattice is over-predicted by 440 {+-} 830 pcm (2{sigma}); the conversion ratio, indicator of the good use of uranium, is also slightly over-predicted: 2 % {+-} 4 % (2{sigma}) and the same for B4C absorber rods worth and soluble boron worth, over-predicted by 2 %, both in the 2 standard deviations range. The radial fission maps of heterogeneities (water-holes, B4C and fertile rods) are well reproduced: maximal (C-E)/E dispersion is 1.3 %, maximal power peak error is 2.7 %. The void reactivity worth is the only parameter poorly calculated with an overprediction of +12.4% {+-} 1.5%. ERASME/R analysis of MOX reactivity, void effect and spectral indexes will contribute to the reevaluation of {sup 241}Am and Plutonium isotopes nuclear data for the next library JEFF3.2. (authors)

  20. Final version, May 2002 Cryogenics Assessment Report

    E-Print Network [OSTI]

    Final version, May 2002 1 Cryogenics Assessment Report M. J. Gouge, J. A. Demko and B. W. Mc shows promise with no moving parts in the cold section of pulse tube and drive units that can be oil cryostats. #12;Final version, May 2002 2 Cryogenics Assessment Report M. J. Gouge, J. A. Demko and B. W. Mc

  1. Sustainability Initiative Task Force Final Report

    E-Print Network [OSTI]

    Sheridan, Jennifer

    UW­Madison Sustainability Initiative Task Force Final Report October 2010 #12;We are pleased to present the final report of the campus Sustainability Task Force. This report fulfills the charge we gave to sustainability for consideration by UW­Madison's leadership and campus community. There are many reasons why

  2. Enhanced State Estimators Final Project Report

    E-Print Network [OSTI]

    Enhanced State Estimators Final Project Report Power Systems Engineering Research Center A National Engineering Research Center Enhanced State Estimators Final Project Report Report Authors Jun Zhu, Ph-373-3051 Fax: 617-373-4431 Email: abur@ece.neu.edu Power Systems Engineering Research Center This is a project

  3. MITILCS/TR-196 FINAL REPORT

    E-Print Network [OSTI]

    Saltzer, Jerome H.

    MITILCS/TR-196 FINAL REPORT OF THE MULTICS KERNEL DESIGN PROJECT Schroeder, Clark, Saltzer & Wells #12;This blankpage was inserted to presenepagination. #12;MIT/LCS/TR-196 FINAL REPORT OF THE MULTICS. The report is in four 8ections: I. A summary of the hiahlight8 of the project, together with a complete li8t

  4. Final report on SNAC 11

    SciTech Connect (OSTI)

    Huber, Patrick

    2013-06-26

    This report details how the $5,000 DOE grant to support the workshop titled “Sterile Neutrinos at the Crossroads” (or SNAC11) was allocated and spent. The SNAC11 workshop covered three days during which there were 28 talks, multiple discussion sessions, a poster session with 9 posters delivered, and an impromptu public lecture on the OPERA superluminal neutrino result by the former project manager of OPERA (this was the first official OPERA talk on the subject in North America). The workshop scientific agenda can be viewed at http://www.cpe.vt.edu/snac/program.html. Emerging out of the workshop discussions, was the idea to write a comprehensive white paper describing the current state of the light sterile neutrino. This effort soon became an international collaboration. The final document, titled “Light Sterile Neutrinos: A White Paper” has nearly 200 authors, is 267 pages long, and cites 730 unique references. It has been posted the preprint archive as arXiv:1204.5379 [hep-ph]. Workshop local organizing committee co-chairs, Patrick Huber and Jonathan Link, are the white paper’s head editors. The white paper’s sections and section editors are as follows: 1. Theory and Motivation (Gabriela Barenboim, Valencia and Werner Rodejohann, MPI Heidelberg) 2. Astrophysical Evidence (Kev Abazajian, UC Irvine and Yvonne Wong, Aachen) 3. Evidence from Oscillation Experiments (Joachim Kopp, FNAL and Bill Louis, LANL) 4. Global Picture (Thierry Lasserre, CEA Saclay and Thomas Schwetz, MPI Heidelberg) 5. Requirements for Future Measurements (Bonnie Fleming, Yale and Joe Formaggio, MIT) 6. Appendix: Possible Future Experiments (Patrick Huber, Virginia Tech and Jon Link, Virginia Tech) In all 56 people participated in the workshop, of these 11 were young scientists. The workshop was covered in a feature article in Science (Science, 334, (2011), 304-306.). The DOE award was spent, as budgeted, as contractual services to VT CPE, which is the unit within the University which organizes conferences. Specifically, the travel cost of the speakers P. Langacker, K. Schreckenbach and P. Vogel was covered as well as bus transportation to KURF and to/from the airport.

  5. Santa Barbara Final Technical Report

    SciTech Connect (OSTI)

    Hacker, Angela; Hansen, Sherman; Watkins, Ashley

    2013-11-30

    This report serves as the Final Report for Santa Barbara County’s Energy Efficiency and Conservation Block Grant (EECBG) BetterBuildings Neighborhood Program (BBNP) award from the U.S. Department of Energy (DOE). This report explains how DOE BBNP funding was invested to develop robust program infrastructure designed to help property owners complete energy improvements, thereby generating substantial outcomes for the local environment and economy. It provides an overview of program development and design within the grant period, program accomplishments and challenges to date, and a plan for the future sustainability of emPower, the County’s innovative clean energy and building efficiency program. During the grant period, Santa Barbara County’s emPower program primarily targeted 32,000 owner occupied, single family, detached residential homes over 25 years old within the County. In order to help these homeowners and their contractors overcome market barriers to completing residential energy improvements, the program developed and promoted six voluntary, market-based service areas: 1) low cost residential financing (loan loss reserve with two local credit unions), 2) residential rebates, 3) local customer service, 4) expert energy advising, 5) workforce development and training, and 6) marketing, education and outreach. The main goals of the program were to lower building energy use, create jobs and develop a lasting regional building performance market. These services have generated important early outcomes and lessons after the program’s first two years in service. The DOE BBNP funding was extended through October 2014 to enable Santa Barbara County to generate continued outcomes. In fact, funding related to residential financing remains wholly available for the foreseeable future to continue offering Home Upgrade Loans to approximately 1,300 homeowners. The County’s investment of DOE BBNP funding was used to build a lasting, effective, and innovative program design that has earned statewide recognition and distinction. As a result of the County’s leadership, the California Energy Commission (CEC) and the California Public Utilities Commission (PUC) offered over $5 million in funding to continue realizing ongoing returns on the initial investment made in developing emPower, alongside remaining (extended) DOE BBNP funds. These new funding sources, accepted by the County Board of Supervisors on June 25, 2013, also allow the program to expand its innovative energy solutions to the broader region, including Ventura and San Luis Obispo Counties.

  6. Final Report Package_Winnebago

    SciTech Connect (OSTI)

    Carolyn Stewart, Director, Red Mountain Energy Partners

    2006-10-31

    The Winnebago Tribe of Nebraska energy options study results will be used to advance the Tribe’s near term energy management objectives. The array of energy options identified allows the Tribe to select those activities that best fit its energy strategies, goals and objectives. During the course of the study, Red Mountain analyzed both energy options and energy organizational alternatives suitable for the Tribe, presented findings to the Tribal Council, and made recommendations regarding each. Work products delivered to the Tribe, and provided in the Final Report included: • A matrix of energy management options applicable to the Tribe, which provided descriptions of particular conservation, efficiency, weatherization, and demand management alternatives. The matrix also provided insight about relative costs of the alternatives, cost/benefit efficacy, ease of implementation, resources for implementing, and observations about each. • A matrix of utility service options applicable to the Tribe, describing each of the four alternatives described above. The matrix also provided insight about key benefits of each option, required resources, costs and timeframe for implementation, funding sources and analysis, and key issues for consideration. • Discussion guides prepared for each meeting between the Energy Committee and Council, and the Tribe’s contractor, Red Mountain Energy Partners, which included preliminary analysis and findings. • A Position Description for the Energy Manager position, which was reviewed by the Tribal HR Department, and used by the Tribe to develop a position posting. • A Utility Code designed for Winnebago to use in establishing its Utility Board, and, ultimately, to provide guidance for the Board’s further development. • A project summary book developed to include all key information, deliverables and utility provider data for the project. Winnebago’s growth trends and expansion plans require the Tribe to play a more active role in assuring that safe, reliable, affordable, and clean energy is available to meet the Reservation’s present and future needs. In considering alternatives to meet these needs, the Tribe intends to maintain alignment between its growth goals, and cultural values of sustainable, environmental stewardship.

  7. Nucleosynthesis Supernova Explosions Final Stages of Stellar Evolution For Take Away Final Stages of Stellar Evolution

    E-Print Network [OSTI]

    Hörandel, Jörg R.

    Nucleosynthesis Supernova Explosions Final Stages of Stellar Evolution For Take Away Final Stages.XII.2006 Seminar on Astroparticle Physics - Cosmic Rays #12;Nucleosynthesis Supernova Explosions Final are supernova explosions and which different types exist? Where do heavy elements come from? #12;Nucleosynthesis

  8. Norcal Prototype LNG Truck Fleet: Final Results

    SciTech Connect (OSTI)

    Not Available

    2004-07-01

    U.S. DOE and National Renewable Energy Laboratory evaluated Norcal Waste Systems liquefied natural gas (LNG) waste transfer trucks. Trucks had prototype Cummins Westport ISXG engines. Report gives final evaluation results.

  9. Formula Sheet for the Final Exam

    E-Print Network [OSTI]

    charlotb

    2011-11-16

    Formula Sheet for the Final Exam. 1. Circle: 2. 2. 2. (. ) (. ) x h. y k r. -. + -. = 2. Parabola (Quadratic function): 2. 2. 2. ( ) (. ) or ( ) where. ,. ( ) or. 2. 4. y f x a x h k b b.

  10. Microsoft Word - Agencies Publish Final Environmental Impact...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    DOE (202) 586-4940 Joe Walsh, USFS (202) 205-1134 Agencies Publish Final Environmental Impact Statement on Energy Corridor Designation in the West WASHINGTON, DC - Four Federal...

  11. Helicopter final assembly critical path analysis

    E-Print Network [OSTI]

    Daigh, Sara L. (Sarah Louise), 1981-

    2012-01-01

    Helicopter final assembly involves the installation of hundreds of components into the aircraft and takes thousands of man-hours. Meeting production targets such as total build days and total aircraft man-hours can be ...

  12. CALIFORNIA ENERGY DEMAND 20122022 FINAL FORECAST

    E-Print Network [OSTI]

    /demographic growth, relatively low electricity and natural gas rates, and relatively low efficiency program CALIFORNIA ENERGY DEMAND 20122022 FINAL FORECAST Volume 1: Statewide Electricity Manager Bill Junker Manager DEMAND ANALYSIS OFFICE Sylvia Bender Deputy Director ELECTRICITY SUPPLY

  13. CALIFORNIA ENERGY DEMAND 20142024 FINAL FORECAST

    E-Print Network [OSTI]

    incorporates relatively high economic/demographic growth, relatively low electricity and natural gas rates CALIFORNIA ENERGY DEMAND 20142024 FINAL FORECAST Volume 2: Electricity Demand Sylvia Bender Deputy Director ELECTRICITY SUPPLY ANALYSIS DIVISION Robert P. Oglesby Executive

  14. CALIFORNIA ENERGY DEMAND 20122022 FINAL FORECAST

    E-Print Network [OSTI]

    incorporates relatively high economic/demographic growth, relatively low electricity and natural gas rates CALIFORNIA ENERGY DEMAND 20122022 FINAL FORECAST Volume 2: Electricity Demand OFFICE Sylvia Bender Deputy Director ELECTRICITY SUPPLY ANALYSIS DIVISION Robert P

  15. CALIFORNIA ENERGY DEMAND 20142024 FINAL FORECAST

    E-Print Network [OSTI]

    relatively high economic/demographic growth, relatively low electricity and natural gas rates CALIFORNIA ENERGY DEMAND 2014­2024 FINAL FORECAST Volume 1: Statewide Electricity Demand Gough Office Manager DEMAND ANALYSIS OFFICE Sylvia Bender Deputy Director ELECTRICITY SUPPLY ANALYSIS

  16. MA 159 Final Exam Memo/Preparation

    E-Print Network [OSTI]

    Owen Davis

    2007-11-17

    The homework for the entire semester is your best guide to what could appear on the Final. Exam. ... The old exams on the webpage are also good to practice.

  17. Final Report Distinguished Speaker Program (DSP) and

    E-Print Network [OSTI]

    Zhou, Chongwu

    Innovation Fund: Final Report Fred Aminzadeh Professor of Petroleum and Electrical Engineering Executive for geothermal energy in Indonesia. Introduction The USC Center for Geothermal Studies (CGS) has been established

  18. Research in High Energy Physics. Final report

    SciTech Connect (OSTI)

    Conway, John S.

    2013-08-09

    This final report details the work done from January 2010 until April 2013 in the area of experimental and theoretical high energy particle physics and cosmology at the University of California, Davis.

  19. Final Report DE-EE0005380 ...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    UNIVERSITY OF TEXAS AT AUSTIN Final Report DE-EE0005380 Assessment of Offshore Wind Farm Effects on Sea Surface, Subsurface and Airborne Electronic Systems Prepared for: U.S....

  20. GPS RISK ASSESSMENT STUDY FINAL REPORT

    E-Print Network [OSTI]

    Ladkin, Peter B.

    GPS RISK ASSESSMENT STUDY FINAL REPORT VS-99-007 JANUARY 1999 M8A01 REVISED Sponsor: Mr. J. R. Ryan PHYSICS LABORATORY 11100 Johns Hopkins Road, Laurel, Maryland 20723-6099 #12;GPS RISK ASSESSMENT STUDY

  1. Texas Toll Road Primer Final Report

    E-Print Network [OSTI]

    Texas Toll Road Primer Final Report PRC 14-3 F #12;Texas Toll Road Primer Texas A&M Transportation ............................................................................................... 11 Texas Legislation and Tolling............................................................ 25 Comparing Texas Toll Facilities to the Nation

  2. Data Network Weather Service Reporting - Final Report

    SciTech Connect (OSTI)

    Michael Frey

    2012-08-30

    A final report is made of a three-year effort to develop a new forecasting paradigm for computer network performance. This effort was made in co-ordination with Fermi Lab's construction of e-Weather Center.

  3. TOUGH2 Software Qualification

    E-Print Network [OSTI]

    2010-01-01

    High-Level Nuclear Waste Management Conference, 1996. Wu,Scientific Basis for Nuclear Waste Management XlI, MaterialsScientific Basis for Nuclear Waste Management, G. L. McVay,

  4. TOUGH2 Software Qualification

    E-Print Network [OSTI]

    2010-01-01

    dominated geothermal systems, Geothermal Resources CouncilPrieto geothermal systems, Geothermal Resources CouncilNumerical modeling of geothermal systems with applications

  5. TOUGH2 Software Qualification

    E-Print Network [OSTI]

    2010-01-01

    Specification (e.g. , heat pipe, infIltration, convection1977. Eastman, G.Y. , The Heat Pipe, Scientific American,analytical solution for heat pipe effects near high level

  6. TOUGH2 Software Qualification

    E-Print Network [OSTI]

    2010-01-01

    1982). 'Capillary pressure, vapor adsorption, and vaporadsorption effects, and vapor pressure single-phase slightlyvapor adsorption, and vapor pressure lowering. They ran the

  7. TOUGH2 Software Qualification

    E-Print Network [OSTI]

    2010-01-01

    site-scale model of Yucca Mountain, Nevada, Report LBL-UZ Site-Scale Model of Yucca Mountain," Submitted to the 7thSite-Scale Model of Yucca Mountain, Nevada," Proceedings of

  8. ITOUGH2 Software Qualification

    E-Print Network [OSTI]

    Fraser, P.

    2010-01-01

    development of the pyrite Se extraction method, and 3)improvement of the extraction methods for elemental Se, 2)application of extraction methods to suspended particulate

  9. TOUGH2 Software Qualification

    E-Print Network [OSTI]

    2010-01-01

    Level Radioactive Waste Management, American Nuclear SOCietyNevada, Radioactive Waste Management and EnvironmentalHigh-Level Nuclear Waste Management Conference, 1996. Wu,

  10. TOUGH2 Software Qualification

    E-Print Network [OSTI]

    2010-01-01

    NUREGICR-4645 (Nuclear Regulatory Commission, Washington,NUREGICR-3097, Nuclear Regulatory Commission, Washington,CA, and Nuclear Regulatory Commission Report NUREGICR4645,

  11. Ameresco ESCO Qualification Sheet

    Energy Savers [EERE]

    customer value and environmental sustainability through energy efficiency measures, alternative energy infrastructure solutions, and innovative facility renewal strategies....

  12. TOUGH2 Software Qualification

    E-Print Network [OSTI]

    2010-01-01

    the Production of Superheated Steam from Fractured Vapor-the production of superheated steam from fractured, vapor-water, or only superheated steam, under constant TOUGH2

  13. Mechanical Systems Qualification Standard

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergyTher i nAand DOE Safetyof Energy ThisSitesStoragePlanning Efforts |3)Whales-2008

  14. Chemical Processing Qualification Standard

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergyTher i n c i p a lCaribElectricSouthApplying2-2002 July 2002 DOE HANDBOOK0 February

  15. I MTI 79TR68 FINAL REPORT

    E-Print Network [OSTI]

    Oak Ridge National Laboratory

    #12;I MTI 79TR68 FINAL REPORT A HIGH SEASONAL PERFORMANCE FACTOR GAS HEAT PUMP FOR THE NORTH;Appendices to Final Report DEMONSTRATION OF A HIGH SPF GAS HEAT PUMP FOR THE NORTH CENTRAL UNITED STATES-1/2-Ton Gas-Fired Heat Pump ............ 3-1 3.2 125-Ton Gas-Fired Heat Pump ........ 3-3 3.3 Competative

  16. Title XVII Final Rule | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankADVANCEDInstallers/ContractorsPhotovoltaicsState ofSavings forTitle XVII Final Rule Title XVII Final Rule

  17. Evaluation of ISDP Batch 2 Qualification Compliance to 512-S, DWPF, Tank Farm, and Saltstone Waste Acceptance Criteria

    SciTech Connect (OSTI)

    Shafer, A.

    2010-05-05

    The purpose of this report is to document the acceptability of the second macrobatch (Salt Batch 2) of Tank 49H waste to H Tank Farm, DWPF, and Saltstone for operation of the Interim Salt Disposition Project (ISDP). Tank 49 feed meets the Waste Acceptance Criteria (WAC) requirements specified by References 11, 12, and 13. Salt Batch 2 material is qualified and ready to be processed through ARP/MCU to the final disposal facilities.

  18. Microsoft Word - acqguide18pt0 March 2011 final | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    acqguide18pt0 March 2011 final Microsoft Word - acqguide18pt0 March 2011 final Microsoft Word - acqguide18pt0 March 2011 final More Documents & Publications Chapter 18 - Emergency...

  19. Microsoft Word - NationalPolicyAssurancesAwardTermsFinal81804...

    Office of Environmental Management (EM)

    NationalPolicyAssurancesAwardTermsFinal81804.doc Microsoft Word - NationalPolicyAssurancesAwardTermsFinal81804.doc Microsoft Word - NationalPolicyAssurancesAwardTermsFinal81804.doc...

  20. ITP Glass: Industrial Glass Bandwidth Analysis Final Report,...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Industrial Glass Bandwidth Analysis Final Report, August 2007 ITP Glass: Industrial Glass Bandwidth Analysis Final Report, August 2007 industrialbandwidth.pdf More Documents &...

  1. Roadmap Finalized for Low-Temperature, Coproduced, and Geopressured...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Roadmap Finalized for Low-Temperature, Coproduced, and Geopressured Technologies Roadmap Finalized for Low-Temperature, Coproduced, and Geopressured Technologies March 23, 2011 -...

  2. EIS-0131: Final Environmental Impact Statement | Department of...

    Office of Environmental Management (EM)

    1: Final Environmental Impact Statement EIS-0131: Final Environmental Impact Statement Initial Northwest Power Act Power Sales Contracts EIS-0131-FEIS-volume1.pdf...

  3. EIS-0050: Final Environmental Impact Statement | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Residential Conservation Service Program EIS-0050: Final Environmental Impact Statement More Documents & Publications EIS-0007: Draft Environmental Impact Statement EIS-0125: Final...

  4. National Fuel Cell Electric Vehicle Learning Demonstration Final...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Fuel Cell Electric Vehicle Learning Demonstration Final Report National Fuel Cell Electric Vehicle Learning Demonstration Final Report This report discusses key analysis results...

  5. Agencies Publish Final Environmental Impact Statement on Energy...

    Broader source: Energy.gov (indexed) [DOE]

    DC - Four Federal agencies today released a Final Programmatic Environmental Impact Statement (Final PEIS) proposing to designate more than 6,000 miles of energy...

  6. Final Report: High Energy Physics Program (HEP), Physics Department...

    Office of Scientific and Technical Information (OSTI)

    Final Report: High Energy Physics Program (HEP), Physics Department, Princeton University Citation Details In-Document Search Title: Final Report: High Energy Physics Program...

  7. Department of Energy and Beacon Power Finalize $43 Million Loan...

    Office of Environmental Management (EM)

    and Beacon Power Finalize 43 Million Loan Guarantee for Innovative Energy Storage Project in New York State Department of Energy and Beacon Power Finalize 43 Million Loan...

  8. EIS-0404: EPA Notice of Availability of the Final Environmental...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Final Environmental Impact Statement EIS-0404: EPA Notice of Availability of the Final Environmental Impact Statement Los Vaqueros Reservoir Expansion Project, California...

  9. EA-1699: Final Environmental Assessment | Department of Energy

    Office of Environmental Management (EM)

    99: Final Environmental Assessment EA-1699: Final Environmental Assessment PopeDouglas Third Combustor Expansion Project, Alexandria, Minnesota The United States Department of...

  10. EIS-0060: Final Environmental Impact Statement | Department of...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Impact Statement EIS-0060: Final Environmental Impact Statement Bonneville Power Administration Proposed FY 1981 Program EIS-0060: Final Environmental Impact Statement...

  11. Wind Forecast Improvement Project Southern Study Area Final Report...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Forecast Improvement Project Southern Study Area Final Report Wind Forecast Improvement Project Southern Study Area Final Report Wind Forecast Improvement Project Southern Study...

  12. Department of Energy Finalizes Regulations to Increase Energy...

    Energy Savers [EERE]

    Finalizes Regulations to Increase Energy Efficiency in New Federal Buildings by 30% Department of Energy Finalizes Regulations to Increase Energy Efficiency in New Federal...

  13. 2011 Final Report - Nano-Oxide Photocatalysis for Solar Energy...

    Office of Scientific and Technical Information (OSTI)

    Technical Report: 2011 Final Report - Nano-Oxide Photocatalysis for Solar Energy Conversion Citation Details In-Document Search Title: 2011 Final Report - Nano-Oxide Photocatalysis...

  14. Final Report Implementing Office of Management and Budget Information...

    Energy Savers [EERE]

    Final Report Implementing Office of Management and Budget Information Dissemination Quality Guidelines (67 Fed Reg 62446) Final Report Implementing Office of Management and Budget...

  15. EIS-0471: Final Environmental Impact Statement | Department of...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    EIS-0468: Final Environmental Impact Statement EA-1607: Final Environmental Assessment Disposition of DOE Excess Depleted Uranium, Natural Uranium, and Low-Enriched Uranium...

  16. EIS-0141: Final Environmental Impact Statement | Department of...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Final Environmental Impact Statement EIS-0141: Final Environmental Impact Statement Washington Water PowerB.C. Hydro Transmission Interconnection Project EIS-0141-FEIS.pdf...

  17. Energy Department Finalizes $337 Million Loan Guarantee to Mesquite...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Finalizes 337 Million Loan Guarantee to Mesquite Solar 1 for Innovative Solar Power Plant Energy Department Finalizes 337 Million Loan Guarantee to Mesquite Solar 1 for...

  18. Finalize Historic National Program to Reduce Greenhouse Gases...

    Open Energy Info (EERE)

    Finalize Historic National Program to Reduce Greenhouse Gases and Improve Fuel Economy for Cars and Trucks Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Finalize...

  19. Final Environmental Assessment of the National Renewable Energy...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Final Environmental Assessment of the National Renewable Energy Laboratory's (NREL) South Table Mountain Complex (DOEEA 1440) Final Environmental Assessment of the National...

  20. Final Report: Enhanced Geothermal Systems Technology Phase II...

    Open Energy Info (EERE)

    Final Report: Enhanced Geothermal Systems Technology Phase II: Animas Valley, New Mexico Jump to: navigation, search OpenEI Reference LibraryAdd to library Report: Final Report:...

  1. DOE Issues Final Request for Proposal for Portsmouth Gaseous...

    Energy Savers [EERE]

    DOE Issues Final Request for Proposal for Portsmouth Gaseous Diffusion Plant Support Services DOE Issues Final Request for Proposal for Portsmouth Gaseous Diffusion Plant Support...

  2. LM Issues Final Programmatic Environmental Impact Statement on...

    Office of Environmental Management (EM)

    Issues Final Programmatic Environmental Impact Statement on the Uranium Leasing Program LM Issues Final Programmatic Environmental Impact Statement on the Uranium Leasing Program...

  3. Final Report for the DOE Chemical Hydrogen Storage Center of...

    Energy Savers [EERE]

    Final Report for the DOE Chemical Hydrogen Storage Center of Excellence Final Report for the DOE Chemical Hydrogen Storage Center of Excellence This technical report describes the...

  4. EIS-0350-SA-02: Final Supplement Analysis | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    350-SA-02: Final Supplement Analysis EIS-0350-SA-02: Final Supplement Analysis Chemistry and Metallurgy Research Building Replacement Project at Los Alamos National Laboratory, Los...

  5. Research in theoretical nuclear and neutrino physics. Final report...

    Office of Scientific and Technical Information (OSTI)

    Research in theoretical nuclear and neutrino physics. Final report Citation Details In-Document Search Title: Research in theoretical nuclear and neutrino physics. Final report The...

  6. EA-1775: Final Environmental Assessment | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Final Environmental Assessment EA-1775: Final Environmental Assessment Texas A&M University Combined Heat and Power Project, College Station, Texas DOE prepared this Environmental...

  7. Final Environmental Impact Report: North Brawley Ten Megawatt...

    Open Energy Info (EERE)

    Final Environmental Impact Report: North Brawley Ten Megawatt Geothermal Demonstration Facility Jump to: navigation, search OpenEI Reference LibraryAdd to library Report: Final...

  8. EIS-0456: EPA Notice of Availability of the Final Environmental...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    EPA Notice of Availability of the Final Environmental Impact Statement EIS-0456: EPA Notice of Availability of the Final Environmental Impact Statement Cushman Hydroelectric...

  9. EIS-0370: EPA Notice of Availability of the Final Environmental...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    EPA Notice of Availability of the Final Environmental Impact Statement EIS-0370: EPA Notice of Availability of the Final Environmental Impact Statement Windy Gap Firming Project,...

  10. EIS-0389: EPA Notice of Availability of the Final Environmental...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    EPA Notice of Availability of the Final Environmental Impact Statement EIS-0389: EPA Notice of Availability of the Final Environmental Impact Statement Trinity Public Utilities...

  11. EIS-0472: EPA Notice of Availability of Final Programmatic Environment...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Final Programmatic Environmental Impact Statement EIS-0472: EPA Notice of Availability of Final Programmatic Environmental Impact Statement Uranium Leasing Program, Mesa, Montrose,...

  12. EIS-0439: EPA Notice of Availability of the Final Environmental...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Final Environmental Impact Statement EIS-0439: EPA Notice of Availability of the Final Environmental Impact Statement Rice Solar Energy Project, Riverside County, CA Notice of...

  13. EIS-0400: EPA Notice of Availability of Final Environmental Impact...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Final Environmental Impact Statement EIS-0400: EPA Notice of Availability of Final Environmental Impact Statement Granby Pumping Plant Switchyard-Windy Gap Substation Transmission...

  14. EIS-0450: EPA Notice of Availability of a Final Environmental...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    EPA Notice of Availability of a Final Environmental Impact Statement EIS-0450: EPA Notice of Availability of a Final Environmental Impact Statement TransWest Express Transmission...

  15. EIS-0357: EPA Notice of Availability of the Final Environmental...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    EPA Notice of Availability of the Final Environmental Impact Statement EIS-0357: EPA Notice of Availability of the Final Environmental Impact Statement Gilberton Coal-to-Clean...

  16. EIS-0387: EPA Notice of Availability of the Final Environmental...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Final Environmental Impact Statement EIS-0387: EPA Notice of Availability of the Final Environmental Impact Statement Y-12 National Security Complex Project, Oak Ridge, Tennessee...

  17. EIS-0382: EPA Notice of Availability of the Final Environmental...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    EPA Notice of Availability of the Final Environmental Impact Statement EIS-0382: EPA Notice of Availability of the Final Environmental Impact Statement Mesaba Energy Project,...

  18. EIS-0423: DOE Notice of Availability of the Final Environmental...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Final Environmental Impact Statement EIS-0423: DOE Notice of Availability of the Final Environmental Impact Statement Long-Term Management and Storage of Elemental Mercury Notice...

  19. EIS-0426: EPA Notice of Availability of the Final Environmental...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    EPA Notice of Availability of the Final Environmental Impact Statement EIS-0426: EPA Notice of Availability of the Final Environmental Impact Statement The Environmental Protection...

  20. EIS-0385: EPA Notice of Availability of the Final Environmental...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    EPA Notice of Availability of the Final Environmental Impact Statement EIS-0385: EPA Notice of Availability of the Final Environmental Impact Statement Site Selection for the...

  1. Final Report: Particulate Emissions Testing, Unit 1, Potomac...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Final Report: Particulate Emissions Testing, Unit 1, Potomac River Generating Station, Alexandria, Virginia Final Report: Particulate Emissions Testing, Unit 1, Potomac River...

  2. EIS-0468: EPA Notice of Availability of the Final Environmental...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    EPA Notice of Availability of the Final Environmental Impact Statement American Centrifuge Plant, Piketon, OH EIS No. 20110153, Final EIS, DOE, OH, ADOPTION-American...

  3. ICP (Institutional Conservation Program) monitoring: Final report

    SciTech Connect (OSTI)

    Not Available

    1986-09-01

    The following pages present the Final Report of activities undertaken by Arawak in carrying out its contractual obligations for the New York Support Office of US Department of Energy. The contract calls for the field monitoring/review of DOE grants to schools and hospitals under the Institutional Conservation Program (ICP). This Final Report is the result of a review of statistics and findings gathered over the period of the contract, which included monitoring visits to 78 grantees in New York State and New Jersey. The report is intended to highlight aspects of the monitoring project and to make recommendations.

  4. Final Workshop of Department's Inaugural Technology Assessment |

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) |Final Report Document Number(Technical Final

  5. Project Final Report UBC LBS Project Services1 Project Final Report UBC LBS Project Services2

    E-Print Network [OSTI]

    is used as a foundation for all development, land use, and transportation activities at UBC. LBS Project Services is a fee-for-service provider of development, design, and project management servicesProject Final Report UBC LBS Project Services1 #12;Project Final Report UBC LBS Project Services2

  6. Enrollment Analysis Final for Fall 2014

    E-Print Network [OSTI]

    Hutcheon, James M.

    Management and Director of Strategic Research and Analysis Project Support: Office of Strategic Research Management and Director of Strategic Research and Analysis o Mr. Paul Wilver, Assistant Director, DecisionEnrollment Analysis Final for Fall 2014 Office of Strategic Research & Analysis November 11, 2014

  7. Final Papers What I look for

    E-Print Network [OSTI]

    Schweik, Charles M.

    Final Papers What I look for: 1. Depth of argument (Are statements specific? Do you provide details:30 am on day of preso #12;Assisted Migration #12;Assisted Migration Synonyms · Managed relocation Migration? Kueppers et al., 2005 Map based on a Bioclimatic Envelope Model #12;What's wrong with normal

  8. Final Vitrification Melter And Vessels Evaluation Documentation

    Broader source: Energy.gov [DOE]

    DOE has prepared final evaluations and made waste incidental to reprocessing determinations for the vitrification melter and feed vessels (the concentrator feed makeup tank and the melter feed hold tank), used by DOE’s West Valley Demonstration Project as part of the process to vitrify waste from prior commercial reprocessing of spent nuclear fuel.

  9. Massively Deployed Sensors Final Project Report

    E-Print Network [OSTI]

    of massive deployment of sensors in electric power systems. There are several areas where the addition of modern, economical sensor technology can improve the quality of a large electric power grid. This reportMassively Deployed Sensors Final Project Report Power Systems Engineering Research Center

  10. Oahu Wind Integration Study Final Report

    E-Print Network [OSTI]

    Oahu Wind Integration Study Final Report Prepared for the U.S. Department of Energy Office, and Debbie Lew provided their expertise on wind and solar data from NREL and contributed to the TRC state in the nation. In 2008 this cost the state approximately $8.4 billion each year, which

  11. IXTOC OIL SPILL ASSESSMENT FINAL REPORT

    E-Print Network [OSTI]

    Miller, Scott

    IXTOC OIL SPILL ASSESSMENT FINAL REPORT EXECUTIVE SUMMARY Prepared for : Bureau of Land Management in input of tar/oil to the Texas Gulf Coast (Geyer ;, 1981) have less of an obvious ecological impact, if any . The Brittany coast of France has been affected for several years by the acute oil input from

  12. Final Year Projects Class of 2012

    E-Print Network [OSTI]

    Humphrys, Mark

    Engineering Page 10 Message from our Sponsor SAP Page 13 Project Areas/Technology Categories Page 15 Operating Systems/Programmes Page 16 Project Index Page 17-18 Projects 1-82 Page 20-101 Companies Sponsoring PrizesFinal Year Projects Class of 2012 schools of computing, electronic engineering and mechanical

  13. Modeling of GE Appliances: Final Presentation

    SciTech Connect (OSTI)

    Fuller, Jason C.; Vyakaranam, Bharat; Leistritz, Sean M.; Parker, Graham B.

    2013-01-31

    This report is the final in a series of three reports funded by U.S. Department of Energy Office of Electricity Delivery and Energy Reliability (DOE-OE) in collaboration with GE Appliances’ through a Cooperative Research and Development Agreement (CRADA) to describe the potential of GE Appliances’ DR-enabled appliances to provide benefits to the utility grid.

  14. Java Security Final Project for ECE578

    E-Print Network [OSTI]

    Java Security Final Project for ECE578: Computer and Network Security by Douglas R. Dechow A Brief History of Java and Java Security The Java language and environment began as an outgrowth of a failed eventually become Java. Given that from the very beginning, the intended application domain for Oak (Java

  15. ENGINEERING EDUCATION IN INDIA Draft Final report

    E-Print Network [OSTI]

    Banerjee, Rangan

    ENGINEERING EDUCATION IN INDIA Draft Final report Rangan Banerjee Vinayak P. Muley Sponsored by Observer Research Foundation Energy Systems Engineering, IIT Bombay Powai, Mumbai ­ 400076 September 14, 2007 #12;i Preface In India engineering is one of the preferred choices for good students at the 10

  16. Final version 11 April 1997 Connecticut

    E-Print Network [OSTI]

    Pollard, David

    Final version 11 April 1997 Connecticut Juror Selection East Hartford Hartford West Hartford Avon, and the whole of Section 7 and Appendix B need major revision. Report to the Connecticut Public Defender The questionnaire data 12 3 Measures of disparity 17 4 The JIS data 19 5 Federal data 26 6 Connecticut population

  17. Final Technical Report: Hawaii Hydrogen Center for

    E-Print Network [OSTI]

    System Modification 16 2.5.2.2 Hydrogen Storage System 16 2.5.2.3 Additional Equipment 19 2.5.2.4 System of the HSS Performance in Steady-State and Stand-Alone Operation 43 2.6.3 Advantages of Hydrogen StorageFinal Technical Report: Hawaii Hydrogen Center for Development and Deployment of Distributed Energy

  18. Biodiesel Engine Testing MECH-457 Final Report

    E-Print Network [OSTI]

    Biodiesel Engine Testing MECH-457 Final Report Submitted to Jon Mikkelsen April 11, 2005 Darren at UBC has begun producing biodiesel fuel from waste cooking oils acquired from campus kitchens. Using biodiesel in a four-cylinder, 30 hp Kubota engine (V1305). This engine was chosen because it is used

  19. AGR-2 Data Qualification Report for ATR Cycles 151B-2, 152A, 152B, 153A, 153B and 154A

    SciTech Connect (OSTI)

    Binh T. Pham; Jeffrey J. Einerson

    2013-09-01

    This report documents the data qualification status of AGR-2 fuel irradiation experimental data from Advanced Test Reactor (ATR) Cycles 152A, 152B, 153A, 153B, and 154A, as recorded in the Nuclear Data Management and Analysis System (NDMAS). The AGR-2 data streams addressed include thermocouple (TC) temperatures, sweep gas data (flow rate, pressure, and moisture content), and fission product monitoring system (FPMS) data for each of the six capsules in the experiment. A total of 13,400,520 every minute instantaneous TC and sweep gas data records were received and processed by NDMAS for this period. Of these data, 8,911,791 records (66.5% of the total) were determined to be Qualified based on NDMAS accuracy testing and data validity assessment. For temperature, there were 4,266,081 records (74% of the total TC data) that were Failed due to TC instrument failures. For sweep gas flows, there were 222,648 gas flow records (2.91% of the flow data) that were Failed. The inlet gas flow failures due to gas flow cross-talk and leakage problems that occurred after Cycle 150A were corrected by using the same gas mixture in all six capsules and the Leadout. For FPMS data, NDMAS received and processed preliminary release rate and release-to-birth rate ratio (R/B) data for three reactor cycles (Cycles 149B, 150B, and 151A) . This data consists of 45,983 release rate records and 45,235 R/B records for the 12 radionuclides reported. The qualification status of these FPMS data has been set to In Process until receipt of Quality Assurance-approved data generator reports. All of the above data have been processed and tested using a SAS®-based enterprise application software system, stored in a secure Structured Query Language database, made available on the NDMAS Web portal (http://ndmas.inl.gov), and approved by the INL STIM for release to both internal and appropriate external Very High Temperature Reactor Program participants.

  20. Final Technical Report - DE-EE0003542

    SciTech Connect (OSTI)

    Haley, James D

    2013-03-31

    Wind has provided energy for thousands of years: some of the earliest windmill engineering designs date back to ancient Babylonia and India where wind would be used as a source of irrigation. Today, wind is the quickest growing resource in Americas expanding energy infrastructure. However, to continue to positively diversify Americas energy portfolio and further reduce the countrys reliance of foreign oil, the industry must grow substantially over the next two decades in both turbine installations and skilled industrial manpower to support. The wind sector is still an emergent industry requiring maturation and development of its labor force: dedicated training is needed to provide the hard and soft skills to support the increasingly complex wind turbine generators as the technology evolves. Furthermore, the American workforce is facing a steep decline in available labor resources as the baby boomer generation enters retirement age. It is therefore vital that a process is quickly created for supporting the next generation of wind technicians. However, the manpower growth must incorporate three key components. First, the safety and technical training curriculum must be standardized across the industry - current wind educational programs are disparate and dedicated standardization programs must be further refined and implemented. Second, it is essential that the wind sector avoid disrupting other energy production industries by cannibalizing workers, which would indirectly affect the rest of Americas energy portfolio. The future wind workforce must be created organically utilizing either young people entering the workforce or train personnel emerging from careers outside of energy production. Third, the training must be quick and efficient as large amounts of wind turbines are being erected each year and this growth is expected to continue until at least 2035. One source that matches these three requirements is personnel transitioning from military service to the civilian sector. Utilizing the labor pool of transitioning military personnel and a dedicated training program specifically tailored to military hard and soft skills, the wind workforce can rapidly expand with highly skilled personnel. A tailored training program also provides career opportunities to an underutilized labor force as the personnel return from active military duty. This projects goal was to create a Wind Workforce Development Program that streamlines the wind technician training process using industry-leading safety programs and building on existing military experience. The approach used was to gather data from the wind industry, develop the curriculum and test the process to ensure it provides adequate training to equip the technicians as they transition from the military into wind. The platform for the curriculum development is called Personal Qualification Standards (PQS), which is based on the program of the same name from the United States Navy. Not only would the program provide multiple delivery methods of training (including classroom, computer-based training and on-the-job training), but it also is a familiar style of training to many military men and women. By incorporating a familiar method of training, it encourages active participation in the training and reduces the time for personnel to grasp the concept and flow of the training requirements. The program was tested for thoroughness, schedule and efficacy using a 5-person pilot phase during the last two years. The results of the training were a reduction in time to complete training and increased customer satisfaction on client project sites. However, there were obstacles that surfaced and required adaptation throughout the project including method of delivery, curriculum development and project schedules and are discussed in detail throughout the report. There are several key recommendations in the report that discuss additional training infrastructure, scalability within additional alternative energy markets and organizational certification through standardization committees.

  1. MA 15400, Fall 2014, Final Exam Information The Final Exam is on ...

    E-Print Network [OSTI]

    math

    2014-12-09

    Dec 16, 2014 ... The Final Exam is on Tuesday, December 16th starting at 8:00 AM in Lambert Fieldhouse. Plan to arrive at least 10 minutes early so you can ...

  2. 1995 PVUSA progress report. Final report

    SciTech Connect (OSTI)

    NONE

    1996-03-01

    Photovoltaics for Utility Scale Applications (PVUSA) is a national public-private partnership that is assessing and demonstrating the viability of utility-scale (US) photovoltaic (PV) electric generation systems and recent developments in PV module technology. This report updates the project`s progress, reviews the status and performance of the various PV installations during 1995, summarizes key accomplishments and conclusions, and serves as the final report under Pacific Gas and Electric Company`s project management.

  3. Dresden 1 plutonium recycle program. Final report

    SciTech Connect (OSTI)

    Bresnick, S.D.

    1980-01-01

    This is the final report on the Dresden 1 Plutonium Recycle Demonstration Program. It covers the work performed from July 1, 1978 to completion, which includes in-pool inspection of two fuel assemblies, removal of two fuel rods, and post-irradiation examination (PIE) of six fuel rods. Appendix A describes the inspection and rod removal operations, and Appendix B describes the PIE work.

  4. 2020-21 Final Resource Adequacy Assessment

    E-Print Network [OSTI]

    1.15 GW · Solar PV 12.7 GW · Current US installed 15.9 GW · Projected by 2021 for PNW 450 MW · Wind Assessment · Using Wind/Solar to Fill the Gap · Potential Recommendations for Council 2 #12;2020 Final retires 730/670 MW · Total loss of 1,330/1,192 MW (nameplate/winter capacity) · Load change 2020 to 2021

  5. Final M-62 info sheet.pmd

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) | SciTechSubmittedEcologist Final

  6. Final Report WSU Grayscale-Abstract.doc

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) |Final Report Document Number

  7. Seismic ruggedness of aged electrical components: Final report (Phase 2)

    SciTech Connect (OSTI)

    Gleason, J.F.

    1987-01-01

    Seismic tests on new and aged components have shown that, for many types of commonly used nuclear plant electrical components, deterioration due to aging does not significantly affect the ability of the components to function during and after a seismic event. This was demonstrated for capacitors, circuit breakers, contactors (motor starters), control station assemblies, electronic alarms, electronics, fuses, fuse blocks, inductors, meters, motors, pressure transmitters, power supplies, relays, RTDs, solenoid valves, terminal blocks, time delay relays, transformers and switches. A few switch types (limit, pressure and rotary) were observed to be more prone to contact chatter in an aged condition than in an unaged condition. However, the ability of these devices to switch during and after shaking was not affected by aging. These results can be referenced to eliminate the cost of aging prior to seismic qualification testing for many types of electrical components.

  8. ATAC Process Proof of Concept Final Report

    SciTech Connect (OSTI)

    Bri Rolston; Sarah Freeman

    2014-03-01

    Researchers at INL with funding from the Department of Energy’s Office of Electricity Delivery and Energy Reliability (DOE-OE) evaluated a novel approach for near real-time consumption of threat intelligence. Demonstration testing in an industry environment supported the development of this new process to assist the electric sector in securing their critical networks. This report provides the reader with an understanding of the methods used during this proof of concept project. The processes and templates were further advanced with an industry partner during an onsite assessment. This report concludes with lessons learned and a roadmap for final development of these materials for use by industry.

  9. Final Report: Performance Engineering Research Institute

    SciTech Connect (OSTI)

    Mellor-Crummey, John

    2014-10-27

    This document is a final report about the work performed for cooperative agreement DE-FC02-06ER25764, the Rice University effort of Performance Engineering Research Institute (PERI). PERI was an Enabling Technologies Institute of the Scientific Discovery through Advanced Computing (SciDAC-2) program supported by the Department of Energy's Office of Science Advanced Scientific Computing Research (ASCR) program. The PERI effort at Rice University focused on (1) research and development of tools for measurement and analysis of application program performance, and (2) engagement with SciDAC-2 application teams.

  10. 1990 Weatherization Assistance Program monitoring. Final report

    SciTech Connect (OSTI)

    Samuels, L.S.

    1992-06-19

    The fiscal year 1990 DOE weatherization programs were monitored in Indiana, Ohio, and Wisconsin. The focus of the monitoring was on a total of 18 subgrantees. Separate reports on the monitoring completed on each site was submitted as well as the final summary report for each state. The scope of monitoring consisted of a review of current contracts, budgets, program operating procedures, staffing, inventory control, financial and procurement procedures, review of client files and audit reports, inspection of completed dwelling units and assessment of monitoring, training, and technical assistance provided by the grantees. A random sampling of completed units were selected and visits were made to inspect these weatherized dwellings.

  11. Final Supplemental Environmental Assessment (EA-1792)

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: AlternativeCommunication3-EDepartmentExerciseCarbon4Department ofFermiSurface,July-S1 FINAL

  12. Final TOPS Rpt-10pt.PDF

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergy A plug-inPPLforLDRD Report to CongressApril 6,Final InformationDepartmentPage 1 o

  13. Microsoft Word - Final EA- ADM.doc

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration wouldMass map shines light on77 PAGE OF PAGESpersonal CERTIFIED MAIL October 18,99 FINAL928

  14. Microsoft Word - Final M135.DOC

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration wouldMass map shines light on77 PAGE OF PAGESpersonal CERTIFIED MAIL October 18,99 FINAL9285 3.

  15. Microsoft Word - HEP2017_FINAL.docx

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration wouldMass map shines light on77 PAGE OF PAGESpersonal CERTIFIED MAIL4 Subject:6, 2010 FINAL1High

  16. Microsoft Word - Norwich Final EA.doc

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration wouldMass map shines light on77 PAGE OFDetection of Hydrates on Gas5 15 BONNEVILLE36 FINAL

  17. SC0007842FinalTech.pdf

    Office of Scientific and Technical Information (OSTI)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield MunicipalTechnical Report:Speeding accessby aLEDSpeeding FINAL2-4260Earth7842 Conference

  18. DOE Final Report 3-28-12

    Office of Scientific and Technical Information (OSTI)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield MunicipalTechnical Report:Speeding accessby a contractorEnergy,DEC03t933 OSTlandFinal Technical Report

  19. Final Technical ReportDOE2011

    Office of Scientific and Technical Information (OSTI)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield MunicipalTechnical Report:Speeding accessby aLED Street Lighting FINAL

  20. FinalReport-3-13

    Office of Scientific and Technical Information (OSTI)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield MunicipalTechnical Report:Speeding accessby aLED Street Lighting FINALDE-FG02-05ER64124 MicrobialFinal

  1. Microsoft Word - Airport_EA_Final.doc

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia NationalSecurityNuclearH-canyon |I6 Page515 Final

  2. Final Information Quality Bulletin for Peer Review

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum12, 2015Executive Order14,Energy 9, 2013FederalCommitteeFinal FYHCP04 OFFICE

  3. Final Participant List | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum12, 2015Executive Order14,Energy 9, 2013FederalCommitteeFinalDOEofParticipant

  4. Final Rule Technical Amendment | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum12, 2015Executive Order14,Energy 9,UNIVERSITY OF TEXAS AT| DepartmentFinal

  5. Notice of Final Rulemaking | Department of Energy

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested Parties -DepartmentAvailable forSite |n t e g r i t(EIS) andApproach |theFinal

  6. Final decisions that led to Y-12

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) |Final Report Document Number(Technical Finaldecisions that

  7. FinalBESDavenportJune1Update

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) |Final Report Document Number(Technical FinaldecisionsBES /

  8. Final_Groundwater_flowchart_June07.indd

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) |Final Report Document Number(TechnicalREMEDIATE AND

  9. EIS-0128: Final Environmental Impact Statement | Department of...

    Energy Savers [EERE]

    8: Final Environmental Impact Statement EIS-0128: Final Environmental Impact Statement California-Oregon Transmission Project EIS-0128-FEIS-volume1.pdf EIS-0128-FEIS-volume2A.pdf...

  10. EIS-0511: FERC Notice of Availability of FInal Environmental...

    Energy Savers [EERE]

    EIS-0511: FERC Notice of Availability of FInal Environmental Impact Statement Aguirre Offshore GasPort Project, Puerto Rico FERC issued a Notice of Availability of the Final EIS...

  11. SOW and Key Performance Parameters (KPP) Handbook Final Version...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    SOW and Key Performance Parameters (KPP) Handbook Final Version 9-30-2014 SOW and Key Performance Parameters (KPP) Handbook Final Version 9-30-2014 This handbook provides suggested...

  12. Applications/Algorithms Roadmapping Activity. First Stage Final Report

    E-Print Network [OSTI]

    Higham, Nicholas J.

    Applications/Algorithms Roadmapping Activity. First Stage Final Report Anne Trefethen, Nicholas J ISSN 1749-9097 #12; Applications/Algorithms Roadmapping Activity First Stage Final Report June ..................................................................................................................................... 9 The HPC/NA Roadmap Activity

  13. LLNL Final Design for PDV Measurements of Godiva for Validation...

    Office of Scientific and Technical Information (OSTI)

    Technical Report: LLNL Final Design for PDV Measurements of Godiva for Validation of Multi-Physics Simulation Citation Details In-Document Search Title: LLNL Final Design for PDV...

  14. EIS-0365: EPA Notice of Availability of the Final Environmental...

    Office of Environmental Management (EM)

    5: EPA Notice of Availability of the Final Environmental Impact Statement EIS-0365: EPA Notice of Availability of the Final Environmental Impact Statement Imperial-Mexicali 230-kV...

  15. EIS-0435: EPA Notice of Availability of the Final Environmental...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Environmental Impact Statement Groton Generation Station Interconnection Agreement, Brown County, South Dakota Notice of Availability for the Final Environmental Impact...

  16. Seneca Nation of Indians Strategic Energy Resource Planning Final Report

    SciTech Connect (OSTI)

    Gina Paradis

    2006-01-17

    Final report for the First Steps Toward Developing Renewable Energy and Energy Efficiency on Tribal Lands grants.

  17. Final Exam Location (REVISED 12/9/08)

    E-Print Network [OSTI]

    2008-12-05

    Dec 15, 2008 ... LAMBERT FIELDHOUSE FINAL EXAMINATIONS SEATING ARRANGEMENT . ~ . - . Approximate scale: I" ~ 30'-0· range 1430 tablet arm chairs ...

  18. ALS Beamline Design Requirements - Revision 1

    E-Print Network [OSTI]

    Heimann, Phil

    2010-01-01

    Mechanical Qualification Final check for seismic safety andqualification to check for hazards related to motorized motions and seismic

  19. Energy Impact Illinois - Final Technical Report

    SciTech Connect (OSTI)

    Olson, Daniel; Plagman, Emily; Silberhorn, Joey-Lin

    2014-02-18

    Energy Impact Illinois (EI2) is an alliance of government organizations, nonprofits, and regional utility companies led by the Chicago Metropolitan Agency for Planning (CMAP) that is dedicated to helping communities in the Chicago metropolitan area become more energy efficient. Originally organized as the Chicago Region Retrofit Ramp-Up (CR3), EI2 became part of the nationwide Better Buildings Neighborhood Program (BBNP) in May 2010 after receiving a $25 million award from the U.S. Department of Energy (DOE) authorized through the American Recovery and Reinvestment Act of 2009 (ARRA). The program’s primary goal was to fund initiatives that mitigate barriers to energy efficiency retrofitting activities across residential, multifamily, and commercial building sectors in the seven-county CMAP region and to help to build a sustainable energy efficiency marketplace. The EI2 Final Technical Report provides a detailed review of the strategies, implementation methods, challenges, lessons learned, and final results of the EI2 program during the initial grant period from 2010-2013. During the program period, EI2 successfully increased direct retrofit activity in the region and was able to make a broader impact on the energy efficiency market in the Chicago region. As the period of performance for the initial grant comes to an end, EI2’s legacy raises the bar for the region in terms of helping homeowners and building owners to take action on the continually complex issue of energy efficiency.

  20. Hydrothermal reaction of fly ash. Final report

    SciTech Connect (OSTI)

    Brown, P.W.

    1994-12-31

    The reactions which occur when fly ash is treated under hydrothermal conditions were investigated. This was done for the following primary reasons. The first of these is to determine the nature of the phases that form to assess the stabilities of these phases in the ambient environment and, finally, to assess whether these phases are capable of sequestering hazardous species. The second reason for undertaking this study was whether, depending on the composition of the ash and the presence of selected additives, it would be possible under hydrothermal conditions to form compounds which have cementitious properties. Formation of four classes of compounds, which bracket likely fly ash compositional ranges, were selected for study. The classes are calcium silicate hydrates, calcium selenates, and calcium aluminosulfates, and silicate-based glasses. Specific compounds synthesized were determined and their stability regions assessed. As part of stability assessment, the extent to which selected hazardous species are sequestered was determined. Finally, the cementing properties of these compounds were established. The results obtained in this program have demonstrated that mild hydrothermal conditions can be employed to improve the reactivity of fly ash. Such improvements in reactivity can result in the formation of monolithic forms which may exhibit suitable mechanical properties for selected applications as building materials. If the ashes involved are considered hazardous, the mechanical properties exhibited indicated the forms could be handled in a manner which facilitates their disposal.

  1. Energy Research and Development Division FINAL PROJECT REPORT

    E-Print Network [OSTI]

    Energy Research and Development Division FINAL PROJECT REPORT Boiler Burner Energy Systems Technologies · Transportation Boiler Burner Energy System Technology Final Report is the final report for the Boiler Burner Energy System Technology project PIR-09-012 conducted by Altex Technologies, Inc

  2. Financial Policy Manual 2137 REVISED FINAL FINANCIAL REPORTS

    E-Print Network [OSTI]

    George, Edward I.

    Financial Policy Manual Page 1 2137 REVISED FINAL FINANCIAL REPORTS Effective: November 2003 Last Services PURPOSE: To ensure that the revised final financial reports are submitted so as to mitigate any of revised final financial reports is generally discouraged but may be necessary in cases that benefit

  3. VIEWLS Final recommendations report Shift Gear to Biofuels

    E-Print Network [OSTI]

    VIEWLS Final recommendations report 1 Shift Gear to Biofuels Results and recommendations from the VIEWLS project November 2005 #12;Shift Gear to Biofuels Final report of the VIEWLS project 2 #12;Shift Gear to Biofuels Final report of the VIEWLS project 3 Preface Biofuels are fuels made from

  4. TANK 40 FINAL SB5 CHEMICAL CHARACTERIZATION RESULTS PRIOR TO NP ADDITION

    SciTech Connect (OSTI)

    Bannochie, C.; Click, D.

    2010-01-06

    A sample of Sludge Batch 5 (SB5) was pulled from Tank 40 in order to obtain radionuclide inventory analyses necessary for compliance with the Waste Acceptance Product Specifications (WAPS). This sample was also analyzed for chemical composition including noble metals. Prior to radionuclide inventory analyses, a final sample of the H-canyon Np stream will be added to bound the Np addition anticipated for Tank 40. These analyses along with the WAPS radionuclide analyses will help define the composition of the sludge in Tank 40 that is currently being fed to DWPF as SB5. At the Savannah River National Laboratory (SRNL) the 3-L Tank 40 SB5 sample was transferred from the shipping container into a 4-L high density polyethylene vessel and solids allowed to settle overnight. Supernate was then siphoned off and circulated through the shipping container to complete the transfer of the sample. Following thorough mixing of the 3-L sample, a 239 g sub-sample was removed. This sub-sample was then utilized for all subsequent analytical samples. Eight separate aliquots of the slurry were digested, four with HNO{sub 3}/HCl (aqua regia) in sealed Teflon{reg_sign} vessels and four in Na{sub 2}O{sub 2} (alkali or peroxide fusion) using Zr crucibles. Due to the use of Zr crucibles and Na in the peroxide fusions, Na and Zr cannot be determined from this preparation. Additionally, other alkali metals, such as Li and K that may be contaminants in the Na{sub 2}O{sub 2} are not determined from this preparation. Three Analytical Reference Glass - 14 (ARG-1) standards were digested along with a blank for each preparation. The ARG-1 glass allows for an assessment of the completeness of each digestion. Each aqua regia digestion and blank was diluted to 1:100 mL with deionized water and submitted to Analytical Development (AD) for inductively coupled plasma - atomic emission spectroscopy (ICPAES) analysis, inductively coupled plasma - mass spectrometry (ICP-MS) analysis of masses 81-209 and 230-252, and cold vapor atomic absorption (CV-AA) analysis for Hg. Equivalent dilutions of the peroxide fusion digestions and blank were submitted to AD for ICP-AES analysis. Tank 40 SB5 supernate was collected from a mixed slurry sample in the SRNL Shielded Cells and submitted to AD for ICP-AES. Weighted dilutions of slurry were submitted for ion chromatography (IC), total inorganic carbon/total organic carbon (TIC/TOC), and total base analyses. The following conclusions were drawn from the analytical results reported here: (1) The elemental ratios of the major elements for the SB5 WAPS sample, whose major Tank 51 Qualification sample component underwent Al dissolution, are similar to those measured for the SB4 WAPS sample. (2) The elemental composition of this sample and the analyses conducted here are reasonable and consistent with DWPF batch data measurements in light of DWPF pre-sample concentration and SRAT product heel contributions to the DWPF SRAT receipt analyses. (3) Fifty percent of the sulfur in the SB5 WAPS sample is insoluble, and this represents a significantly larger fraction than that observed in previous sludge batches. (4) The noble metal and Ag concentrations predicted from the measured values for the Tank 51 Confirmation sample and Tank 40 SB4 WAPS sample using a two-thirds Tank 51, one-third Tank 40 heel blend ratio used to arrive at the final SB5 composition, agree with the values for the Tank 40 SB5 WAPS sample measured for this report.

  5. Revised Final DOE10-7-13

    SciTech Connect (OSTI)

    Gilbreath, Bob; Maples, Manuel G

    2013-10-07

    The project goal was reduction of energy consumption on a group of multi-use buildings. The initial step was to assess the group of buildings and define a set of Energy Conservation Measures (ECM?s) that would return an average energy consumption savings of thirty percent. The assessments defined deficiencies in systems from building envelope to interior lighting. Corrections for the deficiencies were addressed through ECM?s that included: high efficiency lighting, occupancy sensors, programmable thermostats, HVAC upgrades, insulation upgrades, as well as a solar thermal installation to reduce propane consumption. ECM?s were recommended based on calculated energy savings. ECM implementation was performed using licensed professionals across multiple disciplines. Electricians installed new lighting and set up occupancy sensors while plumbers implemented low flow fixtures and insulated water heater systems. A general contractor sealed and repaired building envelopes while overseeing other disciplines. Final energy consumption reductions will exceed thirty percent across nine buildings

  6. RESEM-CA Final Project Report

    SciTech Connect (OSTI)

    Carroll, William

    2004-06-01

    This document is the final deliverable for Project 2.2-Retrofit Tools, in the California Energy Commission Public Interest Energy Research Program for High Performance Commercial Building Systems (PIER-HPCBS). The objective of Project 2.2 is to deliver an updated and California-Customized retrofit analysis tool based on the earlier federally funded RESEM (Retrofit Energy Savings Estimation Method) tool [1]. Specific tasks to accomplish this were identified in PIER HPCBS Report No. E2P2.2T1c, and addressed (a) modernization, (b) enhancement of basic analysis methods and capabilities, (c) adding, modifying, or updating databases for California building types, systems, components, utility rate structures, and weather.

  7. Neurons to algorithms LDRD final report.

    SciTech Connect (OSTI)

    Rothganger, Fredrick H.; Aimone, James Bradley; Warrender, Christina E.; Trumbo, Derek

    2013-09-01

    Over the last three years the Neurons to Algorithms (N2A) LDRD project teams has built infrastructure to discover computational structures in the brain. This consists of a modeling language, a tool that enables model development and simulation in that language, and initial connections with the Neuroinformatics community, a group working toward similar goals. The approach of N2A is to express large complex systems like the brain as populations of a discrete part types that have specific structural relationships with each other, along with internal and structural dynamics. Such an evolving mathematical system may be able to capture the essence of neural processing, and ultimately of thought itself. This final report is a cover for the actual products of the project: the N2A Language Specification, the N2A Application, and a journal paper summarizing our methods.

  8. Final State Interactions in Hypernuclear Decay

    E-Print Network [OSTI]

    A. Parreńo; A. Ramos

    2001-04-27

    We present an update of the One-Meson-Exchange (OME) results for the weak decay of s- and p-shell hypernuclei (Ref. Phys. Rev. C {\\bf 56}, 339 (1997)), paying special attention to the role played by final state interactions between the emitted nucleons. The present study also corrects for a mistake in the inclusion of the $K$ and $K^*$ exchange mechanisms, which substantially increases the ratio of neutron-induced to proton-induced transitions, $\\Gamma_n/\\Gamma_p$. With the most up-to-date model ingredients, we find that the OME approach is able to describe very satisfactorily most of the measured observables, including the ratio $\\Gamma_n/\\Gamma_p$.

  9. Final Technical Progress Report NANOSTRUCTURED MAGNETIC MATERIALS

    SciTech Connect (OSTI)

    Charles M. Falco

    2012-09-13

    This report describes progress made during the final phase of our DOE-funded program on Nanostructured Magnetic Materials. This period was quite productive, resulting in the submission of three papers and presentation of three talks at international conferences and three seminars at research institutions. Our DOE-funded research efforts were directed toward studies of magnetism at surfaces and interfaces in high-quality, well-characterized materials prepared by Molecular Beam Epitaxy (MBE) and sputtering. We have an exceptionally well-equipped laboratory for these studies, with: Thin film preparation equipment; Characterization equipment; Equipment to study magnetic properties of surfaces and ultra-thin magnetic films and interfaces in multi-layers and superlattices.

  10. Clean Energy Works Oregon Final Technical Report

    SciTech Connect (OSTI)

    Jacob, Andria; Cyr, Shirley

    2013-12-31

    In April 2010, the City of Portland received a $20 million award from the U.S. Department of Energy, as part of the Energy Efficiency and Conservation Block Grant program. This award was appropriated under the American Recovery and Reinvestment Act (ARRA), passed by President Obama in 2009. DOE’s program became known as the Better Buildings Neighborhood Program (BBNP). The BBNP grant objectives directed the City of Portland Bureau of Planning and Sustainability (BPS) as the primary grantee to expand the BPS-led pilot program, Clean Energy Works Portland, into Clean Energy Works Oregon (CEWO), with the mission to deliver thousands of home energy retrofits, create jobs, save energy and reduce carbon dioxide emissions.The Final Technical Report explores the successes and lessons learned from the first 3 years of program implementation.

  11. Electromagnetic Pulse from Final Gravitational Stellar Collapse

    E-Print Network [OSTI]

    P. D. Morley; Ivan Schmidt

    2002-01-30

    We employ an effective gravitational stellar final collapse model which contains the relevant physics involved in this complex phenomena: spherical radical infall in the Schwarzschild metric of the homogeneous core of an advanced star, giant magnetic dipole moment, magnetohydrodynamic material response and realistic equations of state (EOS). The electromagnetic pulse is computed both for medium size cores undergoing hydrodynamic bounce and large size cores undergoing black hole formation. We clearly show that there must exist two classes of neutron stars, separated by maximum allowable masses: those that collapsed as solitary stars (dynamical mass limit) and those that collapsed in binary systems allowing mass accretion (static neutron star mass). Our results show that the electromagnetic pulse spectrum associated with black hole formation is a universal signature, independent of the nuclear EOS. Our results also predict that there must exist black holes whose masses are less than the static neutron star stability limit.

  12. AISI Direct Steelmaking Program. Final technical report

    SciTech Connect (OSTI)

    Aukrust, E.

    1994-08-01

    This final report deals with the results of a 5-yr project for developing a more energy-efficient, environmentally friendly, less costly process for producing hot metal than current coke ovens and blast furnaces. In the process, iron ore pellets are smelted in a foamy slag created by reaction of coal char with molten slag to produce CO. The CO further reacts with oxygen, which also reacts with coal volatile matter, to produce the heat necessary to sustain the endothermic reduction reaction. The uncombusted CO and H{sub 2} from the coal are used to preheat and prereduce hematite pellets for the most efficient use of the energy in the coal. Laboratory programs confirmed that the process steps worked. Pilot plant studies were successful. Economic analysis for a 1 million tpy plant is promising.

  13. Final Report: Correctness Tools for Petascale Computing

    SciTech Connect (OSTI)

    Mellor-Crummey, John

    2014-10-27

    In the course of developing parallel programs for leadership computing systems, subtle programming errors often arise that are extremely difficult to diagnose without tools. To meet this challenge, University of Maryland, the University of Wisconsin—Madison, and Rice University worked to develop lightweight tools to help code developers pinpoint a variety of program correctness errors that plague parallel scientific codes. The aim of this project was to develop software tools that help diagnose program errors including memory leaks, memory access errors, round-off errors, and data races. Research at Rice University focused on developing algorithms and data structures to support efficient monitoring of multithreaded programs for memory access errors and data races. This is a final report about research and development work at Rice University as part of this project.

  14. AGR 3/4 Irradiation Test Final As Run Report

    SciTech Connect (OSTI)

    Collin, Blaise P.

    2015-06-01

    Several fuel and material irradiation experiments have been planned for the Idaho National Laboratory Advanced Reactor Technologies Technology Development Office Advanced Gas Reactor Fuel Development and Qualification Program (referred to as the INL ART TDO/AGR fuel program hereafter), which supports the development and qualification of tristructural-isotropic (TRISO) coated particle fuel for use in HTGRs. The goals of these experiments are to provide irradiation performance data to support fuel process development, qualify fuel for normal operating conditions, support development and validation of fuel performance and fission product transport models and codes, and provide irradiated fuel and materials for post irradiation examination and safety testing (INL 05/2015). AGR-3/4 combined the third and fourth in this series of planned experiments to test TRISO coated low enriched uranium (LEU) oxycarbide fuel. This combined experiment was intended to support the refinement of fission product transport models and to assess the effects of sweep gas impurities on fuel performance and fission product transport by irradiating designed-to-fail fuel particles and by measuring subsequent fission metal transport in fuel-compact matrix material and fuel-element graphite. The AGR 3/4 fuel test was successful in irradiating the fuel compacts to the burnup and fast fluence target ranges, considering the experiment was terminated short of its initial 400 EFPD target (Collin 2015). Out of the 48 AGR-3/4 compacts, 42 achieved the specified burnup of at least 6% fissions per initial heavy-metal atom (FIMA). Three capsules had a maximum fuel compact average burnup < 10% FIMA, one more than originally specified, and the maximum fuel compact average burnup was <19% FIMA for the remaining capsules, as specified. Fast neutron fluence fell in the expected range of 1.0 to 5.5×1025 n/m2 (E >0.18 MeV) for all compacts. In addition, the AGR-3/4 experiment was globally successful in keeping the temperature in the twelve capsules relatively flat in a range of temperatures suitable for the measurement of fission product diffusion in compact matrix and structural graphite materials.

  15. Modern Grid Initiative Distribution Taxonomy Final Report

    SciTech Connect (OSTI)

    Schneider, Kevin P.; Chen, Yousu; Chassin, David P.; Pratt, Robert G.; Engel, David W.; Thompson, Sandra E.

    2008-11-01

    This is the final report for the development of a toxonomy of prototypical electrical distribution feeders. Two of the primary goals of the Department of Energy's (DOE) Modern Grid Initiative (MGI) are 'to accelerate the modernization of our nation's electricity grid' and to 'support demonstrations of systems of key technologies that can serve as the foundation for an integrated, modern power grid'. A key component to the realization of these goals is the effective implementation of new, as well as existing, 'smart grid technologies'. Possibly the largest barrier that has been identified in the deployment of smart grid technologies is the inability to evaluate how their deployment will affect the electricity infrastructure, both locally and on a regional scale. The inability to evaluate the impacts of these technologies is primarily due to the lack of detailed electrical distribution feeder information. While detailed distribution feeder information does reside with the various distribution utilities, there is no central repository of information that can be openly accessed. The role of Pacific Northwest National Laboratory (PNNL) in the MGI for FY08 was to collect distribution feeder models, in the SynerGEE{reg_sign} format, from electric utilities around the nation so that they could be analyzed to identify regional differences in feeder design and operation. Based on this analysis PNNL developed a taxonomy of 24 prototypical feeder models in the GridLAB-D simulations environment that contain the fundamental characteristics of non-urban core, radial distribution feeders from the various regions of the U.S. Weighting factors for these feeders are also presented so that they can be used to generate a representative sample for various regions within the United States. The final product presented in this report is a toolset that enables the evaluation of new smart grid technologies, with the ability to aggregate their effects to regional and national levels. The distribution feeder models presented in this report are based on actual utility models but do not contain any proprietary or system specific information. As a result, the models discussed in this report can be openly distributed to industry, academia, or any interested entity, in order to facilitate the ability to evaluate smart grid technologies.

  16. The LiveWire Project final report

    SciTech Connect (OSTI)

    Brown, C.D.; Nelson, T.T. [Enova Technology, San Diego, CA (United States); Kelly, J.C.; Dominguez, H.A. [Paragon Consulting Services, La Verne, CA (United States)

    1997-10-01

    Utilities across the US have begun pilot testing a variety of hardware and software products to develop a two-way communications system between themselves and their customers. Their purpose is to reduce utility operating costs and to provide new and improved services for customers in light of pending changes in the electric industry being brought about by deregulation. A consortium including utilities, national labs, consultants, and contractors, with the support of the Department of Energy (DOE) and the Electric Power Research Institute (EPRI), initiated a project that utilized a hybrid fiber-coax (HFC) wide-area network integrated with a CEBus based local area network within the customers home. The system combined energy consumption data taken within the home, and home automation features to provide a suite of energy management services for residential customers. The information was transferred via the Internet through the HFC network, and presented to the customer on their personal computer. This final project report discusses the design, prototype testing, and system deployment planning of the energy management system.

  17. Indirect Comprehensive Review Board (ICRB). Final Report

    SciTech Connect (OSTI)

    1996-12-01

    Lockheed Martin Idaho Technologies Company (LMITCO) used a systems engineering approach to take the first step toward defining a requirements baseline for all indirect work at the Idaho National Engineering Laboratory. The intent of this effort was to define the requirements for indirect work, identify the activities necessary to meet the requirements, and to produce defensible cost estimates for the work. The result of this effort is a scrubbed-down, defensible budget for all indirect work in FY 1997. Buying power for each dollar of direct work was increased by $.02. Recommendations are identified for improvements to this process in FY 1998. The purpose of this report is twofold. First is to report the final results of the 1996 ICRB process, and second is to document the process used such that incremental improvements may be made in future years. Objectives, processes, and approaches are described to provide a trail for future boards. Appendices contain copies of board composition, documentation of the process, as well as the actual training materials.

  18. WindWaveFloat Final Report

    SciTech Connect (OSTI)

    Alla Weinstein, Dominique Roddier, Kevin Banister

    2012-03-30

    Principle Power Inc. and National Renewable Energy Lab (NREL) have completed a contract to assess the technical and economic feasibility of integrating wave energy converters into the WindFloat, resulting in a new concept called the WindWaveFloat (WWF). The concentration of several devices on one platform could offer a potential for both economic and operational advantages. Wind and wave energy converters can share the electrical cable and power transfer equipment to transport the electricity to shore. Access to multiple generation devices could be simplified, resulting in cost saving at the operational level. Overall capital costs may also be reduced, provided that the design of the foundation can be adapted to multiple devices with minimum modifications. Finally, the WindWaveFloat confers the ability to increase energy production from individual floating support structures, potentially leading to a reduction in levelized energy costs, an increase in the overall capacity factor, and greater stability of the electrical power delivered to the grid. The research conducted under this grant investigated the integration of several wave energy device types into the WindFloat platform. Several of the resulting system designs demonstrated technical feasibility, but the size and design constraints of the wave energy converters (technical and economic) make the WindWaveFloat concept economically unfeasible at this time. Not enough additional generation could be produced to make the additional expense associated with wave energy conversion integration into the WindFloat worthwhile.

  19. Slagging retrofit pulsed coal combustor: Final report

    SciTech Connect (OSTI)

    Not Available

    1987-01-01

    A concept for a novel form of slagging retrofit pulsed coal combustor was tested in the laboratory. The combustor is based on controlled use of a form of high pressure amplitude combustion instability. The approach adopted was to resolve, in single pulse experiments, the basic technical issues arising in the development of the combustor. In a cold flow device, the issues of coal spatial distribution were addressed and a combustor and solids disperser configuration was developed to give uniform coal distribution in the combustor. Single pulse ignition experiments were conducted to determine the pressure rise in combustor, pressure rise-decay times, and coal conversion a function of various operating variables. Coal injection, flame propagation, and blowdown times leading to potential combustor size reduction of three times over steady flow combustors were demonstrated. The results give high pressure exhaust leading to potentially improved downstream heat transfer and reduced boiler size. Finally, zero-, one-, and two-dimensional mathematical models were developed in support of the experiments and also to provide design capability. 11 refs., 43 figs.

  20. Additional EIPC Study Analysis. Final Report

    SciTech Connect (OSTI)

    Hadley, Stanton W; Gotham, Douglas J.; Luciani, Ralph L.

    2014-12-01

    Between 2010 and 2012 the Eastern Interconnection Planning Collaborative (EIPC) conducted a major long-term resource and transmission study of the Eastern Interconnection (EI). With guidance from a Stakeholder Steering Committee (SSC) that included representatives from the Eastern Interconnection States Planning Council (EISPC) among others, the project was conducted in two phases. Phase 1 involved a long-term capacity expansion analysis that involved creation of eight major futures plus 72 sensitivities. Three scenarios were selected for more extensive transmission- focused evaluation in Phase 2. Five power flow analyses, nine production cost model runs (including six sensitivities), and three capital cost estimations were developed during this second phase. The results from Phase 1 and 2 provided a wealth of data that could be examined further to address energy-related questions. A list of 14 topics was developed for further analysis. This paper brings together the earlier interim reports of the first 13 topics plus one additional topic into a single final report.