National Library of Energy BETA

Sample records for qualification final

  1. Heat Treatment Procedure Qualification -- Final Technical Report

    SciTech Connect

    Robert C. Voigt

    2004-10-15

    Heat treatment practices used by steel foundries have been carefully studied as part of comprehensive heat treatment procedure development trials. These studies highlight the relationships between critical heat treatment process control parameters and heat treatment success. Foundry heat treatment trials to develop heat treatment procedure qualification have shed light on the relationship between heat treatment theory and current practices. Furnace load time-temperature profiles in steel foundries exhibit significant differences depending on heat treatment equipment, furnace loading practice, and furnace maintenance. Time-temperature profiles of the furnace control thermocouples can be very different from the time-temperature profiles observed at the center of casting loads in the furnace. Typical austenitrization temperatures and holding times used by steel foundries far exceed what is required for transformation to austenite. Quenching and hardenability concepts were also investigated. Heat treatment procedure qualification (HTPQ) schema to demonstrate heat treatment success and to pre-qualify other alloys and section sizes requiring lesser hardenability have been developed. Tempering success is dependent on both tempering time and temperature. As such, furnace temperature uniformity and control of furnace loading during tempering is critical to obtain the desired mechanical properties. The ramp-up time in the furnace prior to the establishment of steady state heat treatment conditions contributes to the extent of heat treatment performed. This influence of ramp-up to temperature during tempering has been quantified.

  2. AGC-2 Irradiation Data Qualification Final Report

    SciTech Connect

    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

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

    SciTech Connect

    Hull, Laurence C.

    2014-08-01

    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. The report documents qualification of AGC-3 experiment irradiation monitoring data following MCP-2691. This report also documents whether AGC-3 experiment irradiation monitoring data meet the requirements for data collection as specified in technical and functional requirements documents and quality assurance (QA) plans. Data handling is described showing how data are passed from the data collection experiment to the Nuclear Data Management and Analysis System (NDMAS) team. The data structure is described, including data batches, components, attributes, and response variables. The description of the approach to data qualification includes the steps taken to qualify the data and the specific tests used to verify that the data meet requirements. Finally, the current status of the data received by NDMAS from the AGC-3 experiment is presented with summarized information on test results and resolutions. This report addresses all of the irradiation monitoring data collected during the AGC-3 experiment.

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

    SciTech Connect

    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.

  5. AGR-3/4 Final Data Qualification Report for ATR Cycles 151A through 155B-1

    SciTech Connect

    Pham, Binh T.

    2015-03-01

    Analysis System (NDMAS). 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, release to birth rate ratios [R/Bs], and particle failure counts) for each of the twelve capsules in the AGR 3/4 experiment. During Outage Cycle 155A, fourteen flow meters were installed downstream from fourteen FPMS monitors to measure flows from the monitors; qualification status of these data are also included in the report. 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. For ATR Cycles 151A through 154B, 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 INL ART 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. The qualification status of AGR-3/4 irradiation data during the first six cycles were previously reported in INL/EXT-14-31186 document. This report presents data qualification status for the entire AGR-3/4 irradiation.

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

    SciTech Connect

    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

  7. FAQS Gap Analysis Qualification Card - Occupational Safety |...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Occupational Safety FAQS Gap Analysis Qualification Card - Occupational Safety Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences ...

  8. Mechanical Systems Qualification Standard

    Office of Environmental Management (EM)

    June 2008 DOE STANDARD MECHANICAL SYSTEMS QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 ...

  9. Ameresco ESCO Qualification Sheet

    Energy.gov [DOE]

    Document outlines the energy service company (ESCO) qualifications for Ameresco in relation to the U.S. Department of Energy's (DOEs) energy savings performance contracts (ESPC).

  10. Firearms Qualification Courses Manual

    Directives, Delegations, and Other 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.

  11. Photovoltaic Module Qualification Plus Testing

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Photovoltaic Module Qualification Plus Testing Sarah Kurtz, John Wohlgemuth, Michael ... CO 80401 303-275-3000 * www.nrel.gov Photovoltaic Module Qualification Plus Testing ...

  12. Siemens Government Services ESCO Qualification Sheet | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Siemens Government Services ESCO Qualification Sheet Siemens Government Services ESCO Qualification Sheet Fact sheet outlines the energy service company (ESCO) qualification for ...

  13. Firearms Qualification Courses Manual

    Directives, Delegations, and Other 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.

  14. Quality Procedure- Supplier Qualification

    Energy.gov [DOE]

    This procedure establishes the responsibilities and process for supplier qualification activities conducted by Environmental Management (EM) Headquarters (HQ) Office of Standards and Quality Assurance in accordance with EM-QA-001, Environmental Management Quality Assurance Program.

  15. AGR-1 Data Qualification Report

    SciTech Connect

    Michael Abbott

    2010-03-01

    ABSTRACT Projects for the very high temperature reactor (VHTR) Technology Development Office (TDO) 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 has established the NGNP Data Management and Analysis System (NDMAS) to ensure that VHTR data are (1) qualified for use, (2) stored in a readily accessible electronic form, and (3) analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the data streams associated with the first Advanced Gas Reactor experiment (AGR-1), the processing of these data within NDMAS, and reports the 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. They 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) documentation that the data were collected under an NQA-1 or equivalent quality assurance program. The NDMAS database processing and qualification status of the following five data streams is reported in this document: 1. Fuel fabrication data. All data have been processed into the NDMAS database and qualified (1,819 records). 2. Fuel irradiation data. Data from all 13 AGR-1 reactor cycles have been processed into the NDMAS database and tested. Of these, 85% have been qualified and 15% have failed NDMAS accuracy testing. 3. FPMS data. Reprocessed (January 2010) data from all 13 AGR-1 reactor cycles have been processed into the database and capture tested. Final qualification of these data will be recorded after QA approval of an Engineering Calculations and Analysis Report

  16. Facility Representative Qualification Equivalencies Based on...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Facility Representative Qualification Equivalencies Based on Previous Experience Facility Representative Qualification Equivalencies Based on Previous Experience The referenced ...

  17. Staubli TX-90XL robot qualification at the LLIHE.

    SciTech Connect

    Covert, Timothy Todd

    2010-10-01

    The Light Initiated High Explosive (LIHE) Facility uses a robotic arm to spray explosive material onto test items for impulse tests. In 2007, the decision was made to replace the existing PUMA 760 robot with the Staubli TX-90XL. A qualification plan was developed and implemented to verify the safe operating conditions and failure modes of the new system. The robot satisfied the safety requirements established in the qualification plan. A performance issue described in this report remains unresolved at the time of this publication. The final readiness review concluded the qualification of this robot at the LIHE facility.

  18. Firearms Qualification Courses Manual

    Directives, Delegations, and Other 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.

  19. AGR-1 Data Qualification Interim Report

    SciTech Connect

    Machael Abbott

    2009-08-01

    Projects for the very-high-temperature reactor (VHTR) 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 has established the NGNP Data Management and Analysis System (NDMAS) to ensure that VHTR data are (1) qualified for use, (2) stored in a readily accessible electronic form, and (3) analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the data streams associated with the first Advanced Gas Reactor (AGR-1) experiment, the processing of these data within NDMAS, and reports the interim FY09 qualification status of the AGR-1 data to date. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category, which is assigned by the data generator, and 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) documentation that the data were collected under an NQA-1 or equivalent QA program. The interim qualification status of the following four data streams is reported in this document: (1) fuel fabrication data, (2) fuel irradiation data, (3) fission product monitoring system (FPMS) data, and (4) Advanced Test Reactor (ATR) operating conditions data. A final report giving the NDMAS qualification status of all AGR-1 data (including cycle 145A) is planned for February 2010.

  20. Functional Area Qualification Standard Gap Analysis Qualification Cards |

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Department of Energy Gap Analysis Qualification Cards Functional Area Qualification Standard Gap Analysis Qualification Cards Note: 1. Save the document from the website onto your PC and close it. 2. Open the document on your PC. Answer "No" to the question regarding whether to open the documents as read only. Chemical Processing Gap Civil Structural Engineering Gap Construction Management Gap Criticality Safety Gap Emergency Management Gap Environmental Restoration Gap Facility

  1. Functional Area Qualification Standard Qualification Cards | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Energy Qualification Cards Functional Area Qualification Standard Qualification Cards Note: 1. Save the document from the website onto your PC and close it. 2. Open the document on your PC. Answer "No" to the question regarding whether to open the documents as read only. Aviation Manager Aviation Safety Officer Chemical Processing Civil Structural Engineering Confinement Ventilation and Process Gas Treatment Construction Management Criticality Safety Deactivation and

  2. FINAL

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    2 FINAL ENVIRONMENTAL ASSESSMENT FOR EXIDE TECHNOLOGIES ELECTRIC DRIVE VEHICLE BATTERY AND COMPONENT MANUFACTURING INITIATIVE APPLICATION, BRISTOL, TN, AND COLUMBUS, GA U.S. Department of Energy National Energy Technology Laboratory March 2010 DOE/EA-1712 FINAL ENVIRONMENTAL ASSESSMENT FOR EXIDE TECHNOLOGIES ELECTRIC DRIVE VEHICLE BATTERY AND COMPONENT MANUFACTURING INITIATIVE APPLICATION, BRISTOL, TN, AND COLUMBUS, GA U.S. Department of Energy National Energy Technology Laboratory March 2010

  3. Firearms Qualification Courses Manual

    Directives, Delegations, and Other 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.

  4. ORISE: Training and Qualification Programs

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    By completing the program-which features qualification standards and corresponding training activities-DOE personnel build knowledge, skills and confidence to carry out...

  5. Lockheed Martin ESCO Qualification Sheet

    Energy.gov [DOE]

    Document outlines the energy service company (ESCO) qualifications sheet for Lockheed Martin under the Department of Energy's (DOEs) energy savings performance contract (ESPC).

  6. FAQS Gap Analysis Qualification Card Emergency Management

    Energy.gov [DOE]

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

  7. FAQS Gap Analysis Qualification Card - Chemical Processing |...

    Office of Environmental Management (EM)

    Chemical Processing Gap Analysis Qualification Card (77.17 KB) More Documents & Publications FAQS Gap Analysis Qualification Card - Nuclear Explosive Safety Study FAQS Gap Analysis ...

  8. FAQS Qualification Card - NNSA Package Certification Engineer...

    Office of Environmental Management (EM)

    NNSA Package Certification Engineer Qualification Card (43.26 KB) More Documents & Publications FAQS Gap Analysis Qualification Card - Nuclear Explosive Safety Study ...

  9. Advanced Qualification of Additive Manufacturing Materials Workshop

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Advanced Qualification of Additive Manufacturing Materials Workshop Advanced Qualification of Additive Manufacturing Materials Workshop WHEN: Jul 20, 2015 8:30 AM - Jul 21, 2015...

  10. FAQS Qualification Card - Nuclear Safety Specialist | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Programs is a set of common Functional Area Qualification Standards (FAQS) and ... More Documents & Publications FAQS Gap Analysis Qualification Card - Nuclear Safety ...

  11. FAQS Qualification Card - Industrial Hygiene | Department of...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Programs is a set of common Functional Area Qualification Standards (FAQS) and ... More Documents & Publications FAQS Gap Analysis Qualification Card - Industrial Hygiene ...

  12. FAQS Qualification Card - Instrumentation and Control | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Programs is a set of common Functional Area Qualification Standards (FAQS) and ... DOE-STD-1162-2013 FAQS Qualification Card - Chemical Processing FAQS Gap Analysis ...

  13. Consolidated Edison Solutions, Inc. ESCO Qualification Sheet...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Sheet Consolidated Edison Solutions, Inc. ESCO Qualification Sheet Document outlines the energy service company (ESCO) qualifications for ConEdison Solutions. PDF icon ces

  14. RERTR Fuel Developmemt and Qualification Plan

    SciTech Connect

    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

  15. FAQS Qualification Card Waste Management

    Energy.gov [DOE]

    A key element for the Departments 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 Emergency Management

    Energy.gov [DOE]

    A key element for the Departments 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- Aviation Manager

    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- Chemical Processing

    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. FAQS Qualification Card- Construction Management

    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).

  20. Chemical Processing Qualification Standard

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    6-2010 February 2010 DOE STANDARD CHEMICAL PROCESSING QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1176-2010 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/ns/techstds DOE-STD-1176-2010 iv INTENTIONALLY BLANK DOE-STD-1176-2010 v

  1. NORESCO ESCO Qualification Sheet | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    NORESCO ESCO Qualification Sheet NORESCO ESCO Qualification Sheet Document outlines the energy service company (ESCO) qualifications for NORESCO in relation to the U.S. Department of Energy's (DOEs) energy savings performance contracts (ESPC). Download the NORESCO ESCO Qualification Sheet. (173.64 KB)

  2. Technical Qualification Program Accreditation Schedule | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Energy Schedule Technical Qualification Program Accreditation Schedule Technical Qualification Program (TQP) Accreditation Schedule for CY 2013 and 2014. TQP Accreditation Schedule (74.14 KB) More Documents & Publications Technical Qualification Program Self-Assessment Report - Nevada Site Office - 2009 Technical Qualification Program Self-Assessment Report - Richland Operations Office - 2014 FTCP Corrective Action Plan - Revision 1

  3. TOUGH2 software qualification

    SciTech Connect

    Pruess, K.; Simmons, A.; Wu, Y.S.; Moridis, G.

    1996-02-01

    TOUGH2 is a numerical simulation code for multi-dimensional coupled fluid and heat flow of multiphase, multicomponent fluid mixtures in porous and fractured media. It belongs to the MULKOM ({open_quotes}MULti-KOMponent{close_quotes}) family of codes and is a more general version of the TOUGH simulator. The MULKOM family of codes was originally developed with a focus on geothermal reservoir simulation. They are suited to modeling systems which contain different fluid mixtures, with applications to flow problems arising in the context of high-level nuclear waste isolation, oil and gas recovery and storage, and groundwater resource protection. TOUGH2 is essentially a subset of MULKOM, consisting of a selection of the better tested and documented MULKOM program modules. The purpose of this package of reports is to provide all software baseline documents necessary for the software qualification of TOUGH2.

  4. Microsoft Word - Attachment D - Position Qualifications.docx

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    D - POSITION QUALIFICATIONS POSITION QUALIFICATIONS NOTE: If accepted, the labor category and minimum position qualifications proposed will be incorporated into (andor replace)...

  5. FAQS Gap Analysis Qualification Card - Senior Technical Safety...

    Office of Environmental Management (EM)

    FAQS Qualification Card - Senior Technical Safety Manager FAQS Gap Analysis Qualification Card - Chemical Processing FAQS Gap Analysis Qualification Card - Nuclear Explosive Safety ...

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

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

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

  7. FAQS Gap Analysis Qualification Card - Technical Training | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Technical Training FAQS Gap Analysis Qualification Card - Technical Training Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between ...

  8. FAQS Gap Analysis Qualification Card - Industrial Hygiene | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Industrial Hygiene FAQS Gap Analysis Qualification Card - Industrial Hygiene Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between ...

  9. FAQS Gap Analysis Qualification Card - Nuclear Safety Specialist...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Nuclear Safety Specialist FAQS Gap Analysis Qualification Card - Nuclear Safety Specialist Functional Area Qualification Standard Gap Analysis Qualification Cards outline the ...

  10. FAQS Gap Analysis Qualification Card - Quality Assurance | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Quality Assurance FAQS Gap Analysis Qualification Card - Quality Assurance Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between ...

  11. FTCP-08-002, Technical Qualification Program Requalification...

    Energy.gov [DOE] (indexed site)

    More Documents & Publications Technical Qualification Program Self-Assessment Report - Richland Operations Office - 2014 Technical Qualification Program Accreditation Report - ...

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

    Energy.gov [DOE] (indexed site)

    More Documents & Publications Construction, Qualification, and Low Rate Production ... 100,000 Electric Drive Vehicles Construction, Qualification, and Low Rate ...

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

    Energy.gov [DOE] (indexed site)

    KB) More Documents & Publications Construction, Qualification, and Low Rate ... 100,000 Electric Drive Vehicles Construction, Qualification, and Low Rate ...

  14. Functional Area Qualification Standard Reference Guides

    Energy.gov [DOE]

    The reference guides have been developed to address the competency statements in DOE Functional Area Qualification Standard.

  15. Quality Procedure - Personnel Training and Qualification | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    More Documents & Publications Quality Procedure - Supplier Qualification Quality Procedure - MemoCorrespondence Control and Tracking CRAD, Training - Los Alamos National ...

  16. General Technical Base Qualification Standard

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    SENSITIVE DOE-STD-1146-2007 REAFFIRMED: March 2015 DOE STANDARD GENERAL TECHNICAL BASE QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A: Approved for public release; distribution is unlimited ii This document is available on the Department of Energy Technical Standards Program Website at http://energy.gov/ehss/services/nuclear-safety/ department-energy-technical-standards-program

  17. Memorandum, Technical Qualification Program Accreditation Incentives |

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Department of Energy Technical Qualification Program Accreditation Incentives Memorandum, Technical Qualification Program Accreditation Incentives The National Nuclear Security Admin istration (NNSA) Technica l Qualification Program (TQP) was established as a process to ensure Federal technical employees possess the necessary knowledge, skills, and abilities to perform their assigned duties and responsibilities. The TQP enhances the ability of the NNSA and Department of Energy (DOE) to

  18. Technical Qualification Program Accreditation Objectives and Criteria |

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Department of Energy Objectives and Criteria Technical Qualification Program Accreditation Objectives and Criteria The program clearly identifies and documents the process used to demonstrate employee technical competence. TQP Accreditation Objectives and Criteria (40.57 KB) More Documents & Publications Technical Qualification Program Self-Assessment Report - Sandia Site Office - 2012 Technical Qualification Program Self-Assessment Report - Richland Operations Office - 2014 Technical

  19. Technical Qualification Program Accreditation Objectives and...

    Energy.gov [DOE] (indexed site)

    TQP Accreditation Objectives and Criteria (40.57 KB) More Documents & Publications Technical Qualification Program Self-Assessment Report - Sandia Site Office - 2012 Technical ...

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

    Energy.gov [DOE] (indexed site)

    Business Case for TQP Accreditation Incentives (21.27 KB) More Documents & Publications Technical Qualification Program Self-Assessment Report - Los Alamos Site Office - 2007 ...

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

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

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

  2. Advanced Qualification of Additive Manufacturing Workshop

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

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

  3. CEG Solutions LLC ESCO Qualification Sheet

    Energy.gov [DOE]

    Document outlines the energy service company (ESCO) qualifications for CEG Solutions LLC in relation to the U.S. Department of Energy's (DOE) energy savings performance contracts.

  4. Fire Protection Engineering Functional Area Qualification Standard...

    Office of Environmental Management (EM)

    Sponsor for the Department-wide Fire Protection Functional Area Qualification Standard. ... Craig Christenson DOE RL (Team Leader) Dennis Kubicki DOE EH-51 (Assistant Team Leader) ...

  5. Energy Systems Group ESCO Qualification Sheet

    Energy.gov [DOE]

    Document outlines the energy service company (ESCO) qualifications for Energy Systems Group in relation to U.S. Department of Energy (DOE) energy savings performance contracts (ESPC).

  6. Accelerated Stress Testing, Qualification Testing, HAST, Field...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Accelerated Stress Testing, Qualification Testing, HAST, Field Experience This presentation, which was the opening session of the NREL 2013 Photovoltaic Module Reliability Workshop ...

  7. Radiation Protection Functional Area Qualification Standard

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    MEASUREMENT SENSITIVE DOE-STD-1174-2013 November 2013 DOE STANDARD RADIATION PROTECTION FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel ...

  8. Fire Protection Engineering Functional Area Qualification Standard

    Office of Environmental Management (EM)

    FIRE PROTECTION ENGINEERING FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 ...

  9. Industrial Hygiene Functional Area Qualification Standard

    Energy Saver

    STANDARD INDUSTRIAL HYGIENE FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 ...

  10. Senior Technical Safety Manager Functional Area Qualification...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    NOT MEASUREMENT SENSITIVE DOE-STD-1175-2006 October 2006 DOE STANDARD SENIOR TECHNICAL SAFETY MANAGER FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities ...

  11. Instrumentation and Control Functional Area Qualification Standard

    Office of Environmental Management (EM)

    SENSITIVE DOE-STD-1162-2013 June 2013 DOE STANDARD INSTRUMENTATION AND CONTROL FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. ...

  12. Senior Technical Safety Manager Functional Area Qualification...

    Office of Environmental Management (EM)

    NOT MEASUREMENT SENSITIVE DOE-STD-1175-2013 October 2013 DOE STANDARD SENIOR TECHNICAL SAFETY MANAGER FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities ...

  13. Environmental Compliance Functional Area Qualification Standard

    Energy.gov [DOE] (indexed site)

    ENVIRONMENTAL COMPLIANCE FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 ...

  14. Quality Assurance Functional Area Qualification Standard

    Energy Saver

    NOT MEASUREMENT SENSITIVE DOE-STD-1150-2013 December 2013 DOE STANDARD QUALITY ASSURANCE FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel ...

  15. Facility Representative Functional Area Qualification Standard

    Energy.gov [DOE] (indexed site)

    DOE-STD-1151-2010 October 2010 DOE STANDARD FACILITY REPRESENTATIVE FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of ...

  16. Pepco Energy Services ESCO Qualification Sheet

    Office of Energy Efficiency and Renewable Energy (EERE)

    Document outlines the energy service company (ESCO) qualifications for Pepco Energy Services in relation to the U.S. Department of Energy's (DOEs) energy savings performance contracts (ESPC).

  17. History of IEC Qualification Standards (Presentation)

    SciTech Connect

    Wohlhgemuth, J.

    2011-07-01

    This talk will provide a summary of how the IEC PV module qualification tests were developed and review their strengths and limitations.

  18. Constellation NewEnergy ESCO Qualification Sheet

    Energy.gov [DOE]

    Document outlines the energy service company (ESCO) qualifications for Constellation Energy, Inc., in relation to the U.S. Department of Energy's energy savings performance contract (ESPC).

  19. FPL Energy Services ESCO Qualification Sheet

    Energy.gov [DOE]

    Document outlines the energy service company (ESCO) qualifications for FPL Energy Services in relation to the U.S. Department of Energy's (DOEs) energy savings performance contract (ESPC).

  20. Clark Energy Group ESCO Qualification Sheet

    Energy.gov [DOE]

    Document outlines the energy service company (ESCO) qualifications for Clark Energy Group in relation to the U.S. Department of Energy's (DOEs) energy savings performance contracts (ESPC).

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

    U.S. Department of Energy (DOE) - all 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...

  2. FAQS Qualification Card - Confinement Ventilation and Process...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    For each functional area, the FAQS identify the minimum technical competencies and ... More Documents & Publications DOE-STD-1168-2013 FAQS Gap Analysis Qualification Card - ...

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

    Office of Environmental Management (EM)

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

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

    Office of Environmental Management (EM)

    FY15 Technical Qualification Program Self-Assessment Report - Los Alamos Field Office - FY15 The FY15 self-assessment of the Technical Qualifications and Federal Technical ...

  5. FAQS Gap Analysis Qualification Card – Radiation Protection

    Office of Energy Efficiency and Renewable Energy (EERE)

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

  6. FAQS Gap Analysis Qualification Card – Civil Structural Engineering

    Office of Energy Efficiency and Renewable Energy (EERE)

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

  7. FAQS Gap Analysis Qualification Card – Environmental Restoration

    Energy.gov [DOE]

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

  8. FAQS Gap Analysis Qualification Card – Construction Management

    Energy.gov [DOE]

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

  9. FAQS Qualification Card - Electrical Systems and Safety Oversight...

    Office of Environmental Management (EM)

    Electrical Systems and Safety Oversight FAQS Qualification Card - Electrical Systems and Safety Oversight A key element for the Department's Technical Qualification Programs is a ...

  10. FAQS Gap Analysis Qualification Card – Fire Protection Engineering

    Office of Energy Efficiency and Renewable Energy (EERE)

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

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

    Energy.gov [DOE]

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

  12. FAQS Gap Analysis Qualification Card – Facility Representative

    Energy.gov [DOE]

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

  13. FAQS Gap Analysis Qualification Card – Senior Technical Safety Manager

    Energy.gov [DOE]

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

  14. FAQS Gap Analysis Qualification Card – Mechanical Systems

    Office of Energy Efficiency and Renewable Energy (EERE)

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

  15. FAQS Gap Analysis Qualification Card – Criticality Safety

    Energy.gov [DOE]

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

  16. Model Request for Qualifications to Pre-Qualify Energy Service...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Request for Qualifications to Pre-Qualify Energy Service Companies Model Request for Qualifications to Pre-Qualify Energy Service Companies This page contains a model Request for ...

  17. FAQS Gap Analysis Qualification Card – General Technical Base

    Energy.gov [DOE]

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

  18. FAQS Qualification Card - Quality Assurance | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Programs is a set of common Functional Area Qualification Standards (FAQS) and ... More Documents & Publications FAQS Gap Analysis Qualification Card - Quality Assurance ...

  19. FAQS Qualification Card – Radiation Protection

    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).

  20. FAQS Qualification Card – Facility Maintenance Management

    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).

  1. FAQS Qualification Card – Technical Training

    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).

  2. Chapter 9 - Contracting Qualifications | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Chapter 9 - Contracting Qualifications Chapter 9 - Contracting Qualifications 9.4 - Contractor Responsibility Determinations 9.1_Conflict_of_Interest_0.pdf (26.76 KB) 9.2_Performance_Guarantees_0.pdf (16.88 KB) More Documents & Publications AcqGuide9pt2.doc� Chapter 9.2: Performance Guarantees Policy Flash 2016-32

  3. FAQS Qualification Card – Fire Protection Engineering

    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).

  4. FAQS Qualification Card – Facility Representative

    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 Technical Program Manager

    Energy.gov [DOE]

    A key element for the Departments 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 – Mechanical Systems

    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 – Criticality Safety

    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).

  8. FAQS Qualification Card – Occupational Safety

    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 Nuclear Operations Specialist

    Energy.gov [DOE]

    A key element for the Departments 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- Aviation Safety Officer

    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 – Environmental Restoration

    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

    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 – General Technical Base

    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. IHE material qualification tests description and criteria

    SciTech Connect

    Slape, R J

    1984-06-01

    This report describes the qualification tests presently being used at Pantex Plant, Lawrence Livermore National Laboratory, and Los Alamos National Laboratory that are required by the Department of Energy prior to the approval for an explosive as an Insensitive High Explosive (IHE) material. The acceptance criteria of each test for IHE qualification is also discussed. 5 references, 10 figures.

  15. FAQS Qualification Card- Civil Structural Engineering

    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).

  16. FAQS Qualification Card – Weapon Quality Assurance

    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).

  17. FAQS Qualification Card – Environment Compliance

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

    SciTech Connect

    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.

  19. Methods Data Qualification Interim Report

    SciTech Connect

    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. Johnson Controls ESCO Qualification Sheet | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Johnson Controls ESCO Qualification Sheet Johnson Controls ESCO Qualification Sheet Document outlines the energy service company (ESCO) qualifications for Johnson Controls in relation to the U.S. Department of Energy's (DOEs) energy savings performance contracts (ESPC). Download the Johnson Controls ESCO Qualification Sheet. (136.48 KB)

  1. Schneider Electric ESCO Qualification Sheet | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Schneider Electric ESCO Qualification Sheet Schneider Electric ESCO Qualification Sheet Fact sheet outlines the energy service company (ESCO) qualifications for Schneider Electric in relation to the U.S. Department of Energy's (DOEs) energy savings performance contracts (ESPC). Download the Schneider Electric ESCO Qualification Sheet. (96.9 KB

  2. Technical Qualification Program Administrative Forms | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Administrative Forms Technical Qualification Program Administrative Forms TQP Position Evaluation Questionnaire Form and TQP Resource Management Questionnaire Form TQP Position Evaluation Questionnaire Form (7.19 KB) TQP Resource Management Questionnaire Form (12.85 KB) More Documents & Publications Technical Qualification Program Reaccreditation Report - Sandia Site Office Technical Qualification Program Self-Assessment Report - Oak Ridge Office - 2014 Technical Qualification Program

  3. Benham Companies ESCO Qualification Sheet | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Benham Companies ESCO Qualification Sheet Benham Companies ESCO Qualification Sheet Document outlines the energy service company (ESCO) qualifications for Leidos Engineering (part of Benham Companies) in relation to the U.S. Department of Energy's (DOE) energy savings performance contracts (ESPC). Download the Benham Companies ESCO Qualification Sheet. (112.05

  4. Honeywell International ESCO Qualification Sheet | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Honeywell International ESCO Qualification Sheet Honeywell International ESCO Qualification Sheet Document outlines the energy service company (ESCO) qualifications for Honeywell International in relation to the U.S. Department of Energy's (DOEs) energy savings performance contracts (ESPC). Download the Honeywell International ESCO Qualification Sheet. (152.97 KB)

  5. Installation and Final Testing of an On-Line, Multi-Spectrometer Fission Product Monitoring System (FPMS) to Support Advanced Gas Reactor (AGR) Fuel Testing and Qualification in the Advanced Test Reactor

    SciTech Connect

    J. K. Hartwell; D. M. Scates; M. W. Drigert; J. B. Walter

    2006-10-01

    The US Department of Energy (DOE) is initiating tests of reactor fuel for use in an Advanced Gas Reactor (AGR). The AGR will use helium coolant, a low-power-density ceramic core, and coated-particle fuel. A series of eight (8) fuel irradiation tests are planned for the Idaho National Laboratory’s (INL’s) Advanced Test Reactor (ATR). One important measure of fuel performance in these tests is quantification of the fission gas releases over the nominal 2-year duration of each irradiation experiment. This test objective will be met using the AGR Fission Product Monitoring System (FPMS) which includes seven (7) on-line detection stations viewing each of the six test capsule effluent lines (plus one spare). Each station incorporates both a heavily-shielded high-purity germanium (HPGe) gamma-ray spectrometer for quantification of the isotopic releases, and a NaI(Tl) scintillation detector to monitor the total count rate and identify the timing of the releases. The AGR-1 experiment will begin irradiation after October 1, 2006. To support this experiment, the FPMS has been completely assembled, tested, and calibrated in a laboratory at the INL, and then reassembled and tested in its final location in the ATR reactor basement. This paper presents the details of the equipment performance, the control and acquisition software, the test plan for the irradiation monitoring, and the installation in the ATR basement. Preliminary on-line data may be available by the Conference date.

  6. Functional Area Qualification Standards | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Standards Functional Area Qualification Standards Qualification Standard Qualification Standard Number Approved Aviation Manager DOE-STD-1165-2003 (CN-1) 2009-12 Aviation Safety Officer DOE-STD-1164-2003 (CN-1) 2010-01 Chemical Processing DOE-STD-1176-2010 2010-02 Civil/Structural Engineering DOE-STD-1182-2014 2014-09 Confinement Ventilation and Process Gas Treatment DOE-STD-1168-2013 2013-10 Construction Management DOE-STD-1180-2004 2004-03 Criticality Safety DOE-STD-1173-2009 2009-04

  7. FAQS Gap Analysis Qualification Card - Waste Management | Department of

    Office of Environmental Management (EM)

    Energy Technical Training FAQS Gap Analysis Qualification Card - Technical Training Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard. Technical Training Gap Analysis Qualification Card (83.77 KB) More Documents & Publications DOE-STD-1179-2004 DOE-HDBK-1078-94 FAQS Reference Guide - Technical Training Energy

    Waste Management FAQS Gap Analysis Qualification Card - Waste Management

  8. Criticality Safety Functional Area Qualification Standard

    Energy.gov [DOE] (indexed site)

    DOE-STD-1173-2009 April 2009 DOE STANDARD CRITICALITY SAFETY FUNCTIONAL AREA QUALIFICATION STANDARD DOE Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG ...

  9. Test Cloth Qualification | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Cloth Qualification Test Cloth Qualification The Department of Energy (DOE) develops standardized data templates for reporting the results of tests conducted in accordance with current DOE test procedures. Templates may be used by third-party laboratories under contract with DOE that conduct testing in support of ENERGY STAR® verification, DOE rulemakings, and enforcement of the federal energy conservation standards. Test Cloth Correction Factors -- v2.0 (64.84 KB) More Documents &

  10. New geothermal site identification and qualification. Final report

    SciTech Connect

    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.

  11. 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 ...

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

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Construction, Qualification, and Low Rate Production Start-up of a DC Bus Capacitor High ... Construction, Qualification, and Low Rate Production Start-up of a DC Bus Capacitor High ...

  13. Component and System Qualification Workshop Proceedings | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Energy Component and System Qualification Workshop Proceedings Component and System Qualification Workshop Proceedings Proceedings from the U.S. DOE Hydrogen Component and System Qualification Workshop, held at Sandia National Laboratory in Livermore, CA, on November 4, 2010. Component and System Qualification Workshop Proceedings (106.01 KB) More Documents & Publications CSA International Certification Discussion Hydrogen Technology Workshop Certification and Listing Process and

  14. Technical Qualification Program Accreditation Pros and Cons | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Energy Pros and Cons Technical Qualification Program Accreditation Pros and Cons Business Case for Accreditation Incentives - Challenge the Enterprise to Foster Confidence and Support of TQP Accreditation TQP Accreditation Lessons Learned TQP Accreditation Pros and Cons (75.22 KB) More Documents & Publications Technical Qualification Program Reaccreditation Report - Y-12 Site Office Technical Qualification Program Reaccreditation Report - Sandia Site Office Technical Qualification

  15. Business Case for Technical Qualification Program Accreditation Incentives

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    | Department of Energy Business Case for Technical Qualification Program Accreditation Incentives Business Case for Technical Qualification Program Accreditation Incentives TQP Accreditation standardize the program throughout the Department by ensuring consistent application of TQP requirements. Business Case for TQP Accreditation Incentives (21.27 KB) More Documents & Publications Technical Qualification Program Self-Assessment Report - Los Alamos Site Office - 2007 Technical

  16. Quality Assurance Functional Area Qualification Standard

    Directives, Delegations, and Other Requirements [Office of Management (MA)]

    2013-12-02

    The Quality Assurance (QA) Functional Area Qualification Standard (FAQS) establishes common functional area competency requirements for all DOE QA personnel who provide assistance, direction, guidance, oversight, or evaluation of contractor technical activities that could impact the safe operation of DOE’s defense nuclear facilities.

  17. Quality Assurance Functional Area Qualification Standard

    Directives, Delegations, and Other Requirements [Office of Management (MA)]

    2002-04-22

    Replaced by DOE-1150-2013 This QA Functional Area Qualification Standard establishes common functional area competency requirements for DOE personnel who provide assistance, direction, guidance, oversight, or evaluation of contractor technical QA activities impacting the safe operation of defense nuclear facilities.

  18. Low-level radioactive waste form qualification testing

    SciTech Connect

    Sohal, M.S.; Akers, D.W.

    1998-06-01

    This report summarizes activities that have already been completed as well as yet to be performed by the Idaho National Engineering and Environmental Laboratory (INEEL) to develop a plan to quantify the behavior of radioactive low-level waste forms. It briefly describes the status of various tasks, including DOE approval of the proposed work, several regulatory and environmental related documents, tests to qualify the waste form, preliminary schedule, and approximate cost. It is anticipated that INEEL and Brookhaven National Laboratory will perform the majority of the tests. For some tests, services of other testing organizations may be used. It should take approximately nine months to provide the final report on the results of tests on a waste form prepared for qualification. It is anticipated that the overall cost of the waste quantifying service is approximately $150,000. The following tests are planned: compression, thermal cycling, irradiation, biodegradation, leaching, immersion, free-standing liquid tests, and full-scale testing.

  19. AGR-2 Data Qualification Interim Report

    SciTech Connect

    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).

  20. Advanced Qualification of Additive Manufacturing Workshop

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Additive Manufacturing Workshop Poster Abstract Submission - deadline July 10, 2015 Advanced Qualification of Additive Manufacturing Materials using in situ sensors, diagnostics and modeling Contact Institute Director Dr. Alexander V. Balatsky Institute for Materials Science (505) 665-0077 Email Deputy Director Dr. Jennifer S. Martinez Institute for Materials Science (505) 665-0045 Email Deputy Director Dr. Nathan A. Mara Institute for Materials Science (505) 667 8665 Email Institute

  1. Advanced Qualification of Additive Manufacturing Workshop

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Additive Manufacturing Workshop Advanced Qualification of Additive Manufacturing Materials (AM) Workshop Our goal is to define opportunities and research gaps within additive manufacturing (AM) and to engage the broader scientific/engineering community to discuss future research directions. thumbnail of thumbnail of Contact Institute Director Dr. Alexander V. Balatsky Institute for Materials Science (505) 665-0077 Email Deputy Director Dr. Jennifer S. Martinez Institute for Materials Science

  2. Nuclear Safety Specialist Functional Area Qualification Standard

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    83-2007 November 2007 DOE STANDARD NUCLEAR SAFETY SPECIALIST FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1183-2007 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-STD-1183-2007 iv INTENTIONALLY BLANK

  3. Nuclear Safety Specialist Functional Area Qualification Standard

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    STD-1183-2016 October 2016 DOE STANDARD NUCLEAR SAFETY SPECIALIST FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A: Approved for public release; distribution is unlimited NOT MEASUREMENT SENSITIVE DOE-STD-1183-2016 ii This document is available on the Department of Energy Technical Standards Program Website at http://energy.gov/ehss/services/nuclear-safety/

  4. Occupational Safety Functional Area Qualification Standard

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    11 July 2011 DOE STANDARD OCCUPATIONAL SAFETY FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE DOE-STD-1160-2011 ii This document is available on the Department of Energy Technical Standards Program website at http://www.hss.energy.gov/nuclearsafety/ns/techstds/ DOE-STD-1160-2011 iv

  5. High Temperature Materials Interim Data Qualification Report

    SciTech Connect

    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.

  6. Request for Qualifications for Sacramento Landfill

    Energy.gov [DOE]

    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.

  7. Safeguards and Security Functional Area Qualification Standard

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    1-2009 May 2009 DOE STANDARD SAFEGUARDS AND SECURITY FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1171-2009 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-STD-1171-2009 iii APPROVAL The Federal

  8. Aviation Manager Functional Area Qualification Standard

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    DOE-STD-1165-2003 September 2003 CHANGE NOTICE NO. 1 December 2009 DOE STANDARD AVIATION MANAGER FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1165-2003 CH-1 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/

  9. Aviation Safety Officer Functional Area Qualification Standard

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    64-2003 September 2003 CHANGE NOTICE NO. 1 January 2010 DOE STANDARD AVIATION SAFETY OFFICER FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1164-2003 CH-1 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/

  10. Heat Treatment Procedure Qualification for Steel Castings

    SciTech Connect

    Mariol Charles; Nicholas Deskevich; Vipin Varkey; Robert Voigt; Angela Wollenburg

    2004-04-29

    Heat treatment practices used by steel foundries have been carefully studied as part of comprehensive heat treatment procedure qualification development trials. These studies highlight the relationships between critical heat treatment process control parameters and heat treatment success. Foundry heat treatment trials to develop heat treatment procedure qualifications have shed light on the relationship between heat treatment theory and current practices. Furnace load time-temperature profiles in steel foundries exhibit significant differences depending on heat treatment equipment, furnace loading practice, and furnace maintenance. Time-temperature profiles of furnace control thermocouples can be very different from the time-temperature profiles observed at the center of casting loads in the furnace. Typical austenitization temperatures and holding times used by steel foundries far exceed what is required for transformation to austenite. Quenching and hardenability concepts were also investigated. Heat treatment procedure qualification (HTPQ) schema to demonstrate heat treatment success and to pre-qualify other alloys and section sizes requiring lesser hardenability have been developed. Tempering success is dependent on both tempering time and temperature. As such, furnace temperature uniformity and control of furnace loading during tempering is critical to obtain the desired mechanical properties. The ramp-up time in the furnace prior to the establishment of steady state heat treatment conditions contributes to the extent of heat treatment performed. This influence of ramp-up to temperature during tempering has been quantified.

  11. Microsoft Word - Attachment D - Position Qualifications.docx

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    D - POSITION QUALIFICATIONS POSITION QUALIFICATIONS NOTE: If accepted, the labor category and minimum position qualifications proposed will be incorporated into (and/or replace) the below listing. Historical Allocation (FTE) DESCRIPTION Program Manager 1 Requirements for the Program Manager include a Bachelors or higher degree in a social science, business, or related field; at least 10 years of supervisory and management experience of which 5 years must be in the operation, administration,

  12. Technical Qualification Program Self-Assessment Report - Los Alamos Field

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Office - 2014 | Department of Energy Los Alamos Field Office - 2014 Technical Qualification Program Self-Assessment Report - Los Alamos Field Office - 2014 This self-assessment for the Verification of the Closure of Federal Training & Qualification Deficiencies was conducted to provide Los Alamos Field Office (NA-LA) management specific information related to effectiveness of the closure actions for Federal Training and Qualification (T &Q) deficiencies identified by a recent

  13. Lightning arrestor connector lead magnesium niobate qualification pellet test procedures.

    SciTech Connect

    Tuohig, W.; Mahoney, Patrick A.; Tuttle, Bruce Andrew; Wheeler, Jill Susanne

    2009-02-01

    Enhanced knowledge preservation for DOE DP technical component activities has recently received much attention. As part of this recent knowledge preservation effort, improved documentation of the sample preparation and electrical testing procedures for lead magnesium niobate--lead titanate (PMN/PT) qualification pellets was completed. The qualification pellets are fabricated from the same parent powders used to produce PMN/PT lightning arrestor connector (LAC) granules at HWF&T. In our report, the procedures for fired pellet surface preparation, electrode deposition, electrical testing and data recording are described. The dielectric measurements described in our report are an information only test. Technical reasons for selecting the electrode material, electrode size and geometry are presented. The electrical testing is based on measuring the dielectric constant and dissipation factor of the pellet during cooling from 280 C to 220 C. The most important data are the temperature for which the peak dielectric constant occurs (Curie Point temperature) and the peak dielectric constant magnitude. We determined that the peak dielectric constant for our procedure would be that measured at 1 kHz at the Curie Point. Both the peak dielectric constant and the Curie point parameters provide semi-quantitative information concerning the chemical and microstructural homogeneity of the parent material used for the production of PMN/PT granules for LACs. Finally, we have proposed flag limits for the dielectric data for the pellets. Specifically, if the temperature of the peak dielectric constant falls outside the range of 250 C {+-} 30 C we propose that a flag limit be imposed that will initiate communication between production agency and design agency personnel. If the peak dielectric constant measured falls outside the range 25,000 {+-} 10,000 we also propose that a flag limit be imposed.

  14. 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 ...

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

    Office of Environmental Management (EM)

    2014 Technical Qualification Program Self-Assessment Report - Los Alamos Field Office - 2014 This self-assessment for the Verification of the Closure of Federal Training & ...

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

    Office of Environmental Management (EM)

    Richland Operations Office - 2014 Technical Qualification Program Self-Assessment Report - Richland Operations Office - 2014 The Richland Operations Office (RL) Technical ...

  17. 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 ...

  18. CRAD, NNSA - Federal Employee Training and Qualification Program...

    Office of Environmental Management (EM)

    & Publications CRAD, NNSA - Facility Representatives (FR) Technical Qualification Program Self-Assessment Report - NNSA Production Office - 2014 CRAD, NNSA - Contractor Training...

  19. Electrical Systems And Safety Oversight Functional Area Qualification...

    Energy.gov [DOE] (indexed site)

    SYSTEMS AND SAFETY OVERSIGHT FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 ...

  20. BLM Manual 2803: Qualifications for Holding FLPMA Grants | Open...

    OpenEI (Open Energy Information) [EERE & EIA]

    search OpenEI Reference LibraryAdd to library PermittingRegulatory Guidance - GuideHandbook: BLM Manual 2803: Qualifications for Holding FLPMA GrantsPermitting...

  1. New Geothermal Site Identification and Qualification | Open Energy...

    OpenEI (Open Energy Information) [EERE & EIA]

    Citation Geothermex Inc.. 2004. New Geothermal Site Identification and Qualification. Richmond, CA: California Energy Commission. Report No.: P500-04-051. Contract No.: 500-04-051....

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

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

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

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

    SciTech Connect

    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.

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

    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...

  5. Large Bore Powder Gun Qualification (U)

    SciTech Connect

    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.

  6. FAQS Qualification Card – Nuclear Explosive Safety Study

    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).

  7. FAQS Qualification Card – Confinement Ventilation and Process Gas Treatment

    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 – Safety Software Quality Assurance

    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 – Senior Technical Safety Manager

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

    SciTech Connect

    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.

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

    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. Technical Qualification Program Self-Assessment Report - Richland

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Operations Office - 2014 | Department of Energy Richland Operations Office - 2014 Technical Qualification Program Self-Assessment Report - Richland Operations Office - 2014 The Richland Operations Office (RL) Technical Qualification Program Plan establishes a process to objectively determine that individuals performing activities related to the technical support, management, oversight, or operation possess the necessary knowledge, skills, and abilities to perform their assigned duties and

  13. Essential elements of an effective data qualification

    SciTech Connect

    Jenkins, E.W.

    1994-07-01

    Before data is used in any statistical evaluation, it should be subjected to a thorough data qualification to ensure its integrity. Data Qualification efforts may vary in scope but should all contain certain basic elements. Outliers should be eliminated so that any estimates obtained from the data will not be overly biased. Plots may be generated to uncover potential outliers, and these observations can be confirmed as being anomalous through the use of statistical testing. Non-stationarity of the data (i.e., time trends) may also be initially identified through the use of plots and confirmed by the results of statistical analyses, e.g., the use of the Kendall`s tau statistic. When the dataset has been qualified, replicates and duplicates should be averaged to create a pseudo-independence between data points. An algorithm based on the groundwater data from the Savannah River Site has been used by the Applied Statistics Group at Westinghouse Savannah River Company for this.

  14. Waste Form Qualification Compliance Strategy for Bulk Vitrification

    SciTech Connect

    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.

  15. Technical Qualification Program Self-Assessment Report- Los Alamos Site Office- 2007

    Energy.gov [DOE]

    The Federal Technical Capability Manual requires periodic self-assessment of the effectiveness of the implementation of the Manual and the Technical Qualification Program utilizing a defined set of Objectives and Criteria. The assessment documented by this report is the first periodic review conducted at LASO to meet this requirement. The assessment results are intended to establish a base-line on which to develop and improve the program so no final grade was assigned; however, only six of the twelve Objectives were identified as being met.

  16. Equipment qualification issues research and resolution: Status report

    SciTech Connect

    Bonzon, L.L.; Wyant, F.J.; Bustard, L.D.; Gillen, K.T.

    1986-11-01

    Since its inception in 1975, the Qualification Testing Evaluation (QTE) Program has produced numerous results pertinent to equipment qualification issues. Many have been incorporated into Regulatory Guides, Rules, and industry practices and standards. This report summarizes the numerous reports and findings to date. Thirty separate issues are discussed encompassing three generic areas: accident simulation methods, aging simulation methods, and special topics related to equipment qualification. Each issue-specific section contains (1) a brief description of the issue, (2) a summary of the applicable research effort, and (3) a summary of the findings to date.

  17. Trane U.S. Inc. ESCO Qualification Sheet | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Trane U.S. Inc. ESCO Qualification Sheet Trane U.S. Inc. ESCO Qualification Sheet Document outlines the energy service company (ESCO) qualifications for Trane U.S. Inc. in relation to the U.S. Department of Energy's energy savings performance contracts. Download the Trane qualification sheet. (6.32 MB) More Documents & Publications Trane U.S. Inc. ESCO Qualification Sheet Boiler Upgrades and Decentralizing Steam Systems Save Water and Energy at Naval Air Station Oceana 2016 Washington Native

  18. 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 ...

  19. Testing, Evaluation, and Qualification of Bio-Oil for Heating...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Testing, Evaluation, and Qualification of Bio-Oil for Heating March 26, 2015 Dr. Thomas A. ... of 20% of the petroleum-derived heating oil in the Northeast with infrastructure ...

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

    SciTech Connect

    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

  1. 40 MM Grenade Launcher Qualification Requirements at Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Sites, IG-0806 | Department of Energy 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 The Department of Energy and its National Nuclear Security Administration (NNSA), operate some of the most sensitive Federal facilities in the United States. Because of the mission requirements, safeguards and security is a top priority at these sites. As part of its security

  2. Central Characterization Program (CCP) Training and Qualification Plan |

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Department of Energy Training and Qualification Plan Central Characterization Program (CCP) Training and Qualification Plan This document was used to determine facts and conditions during the Department of Energy Accident Investigation Board's investigation into the radiological release event at the Waste Isolation Pilot Plant. Additional documents referenced and listed in the Phase 2 Radiological Release Event at the Waste Isolation Pilot Plant on February 14, 2014, report in Attachment F.

  3. Model Energy Service Company Pre-Qualification Contract | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Energy Energy Service Company Pre-Qualification Contract Model Energy Service Company Pre-Qualification Contract This page provides model documents for developing a contract between an Energy Service Company (ESCO) and a state energy office (or other entity managing a performance contracting program). This model contract establishes requirements for each pre-qualified ESCO to provide performance contracting services for the program. Requirements include data collection and reporting,

  4. An overview of component qualification using Bayesian statistics and energy

    Office of Scientific and Technical Information (OSTI)

    methods. (Technical Report) | SciTech Connect An overview of component qualification using Bayesian statistics and energy methods. Citation Details In-Document Search Title: An overview of component qualification using Bayesian statistics and energy methods. The below overview is designed to give the reader a limited understanding of Bayesian and Maximum Likelihood (MLE) estimation; a basic understanding of some of the mathematical tools to evaluate the quality of an estimation; an

  5. Technical Qualification Program Self-Assessment Report - Office of Science

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    - 2013 | Department of Energy Office of Science - 2013 Technical Qualification Program Self-Assessment Report - Office of Science - 2013 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

  6. Technical Qualification Program and FTCP Assessment CRADs | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Energy and FTCP Assessment CRADs Technical Qualification Program and FTCP Assessment CRADs This document provides guidance and objectives and criteria to support assessments required by DOE O 426.1 Federal Technical Capability (FTC), Section 4. REQUIREMENTS, paragraph b. FTC Program Implementation, subparagraph (7) Self-Assessment. FTCP and TQP Assessment CRADs, 2012 (60.96 KB) More Documents & Publications Technical Qualification Program Self-Assessment Report - Richland Operations

  7. Environmental Qualification at Savannah River Site

    SciTech Connect

    Martin, S.A.; Murphy, S.L.; Riley, P.J.; Sharma, M.K.; Sheikh, N.A.; Weister, T.E.

    1992-01-01

    The objective of Environmental Qualification (EQ) is to demonstrate that equipment essential to the mitigation of consequences from, and monitoring of plant conditions following Design Basis Accidents (DBAs) will operate as intended under normal/abnormal and accident environmental conditions over the installed life. For example, if a component is needed to maintain the reactor in a safe shutdown condition during an accident, and if the component is subjected to a harsh environment during that accident, then documentation must be prepared addressing the ability of the equipment to work properly in the accident environment. The requirement for an EQ program at SRS was mandated by the Department of Energy (DOE) K-Reactor Safety Evaluation Report (SER) which requires SRS to: (1) provide a long term plan for an EQ program with DOE approval prior to restart and (2) prepare and submit to DOE, Justifications for Continued Operations, that justify restarting and operating the K-Reactor until a long term compliance can be achieved with DOE approval.

  8. Workshop on environmental qualification of electric equipment

    SciTech Connect

    Lofaro, R.; Gunther, W.; Villaran, M.; Lee, B.S.; Taylor, J.

    1994-05-01

    Questions concerning the Environmental Qualification (EQ) of electrical equipment used in commercial nuclear power plants have recently become the subject of significant interest to the US Nuclear Regulatory Commission (NRC). Initial questions centered on whether compliance with the EQ requirements for older plants were adequate to support plant operation beyond 40 years. After subsequent investigation, the NRC Staff concluded that questions related to the differences in EQ requirements between older and newer plants constitute a potential generic issue which should be evaluated for backfit, independent of license renewal activities. EQ testing of electric cables was performed by Sandia National Laboratories (SNL) under contract to the NRC in support of license renewal activities. Results showed that some of the environmentally qualified cables either failed or exhibited marginal insulation resistance after a simulated plant life of 20 years during accident simulation. This indicated that the EQ process for some electric cables may be non-conservative. These results raised questions regarding the EQ process including the bases for conclusions about the qualified life of components based upon artificial aging prior to testing.

  9. Secondary Waste Cast Stone Waste Form Qualification Testing Plan

    SciTech Connect

    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

  10. DOE-STD-1176-2004; Chemical Processing Functional Area Qualification...

    Office of Environmental Management (EM)

    ... standards, guides, regulations, Department of Energy Orders, and accepted practices. ... * Training and qualification * Regulatory compliance * Workplace and process ...

  11. FTCP-08-001, Methodology for Counting TQP Personnel and Qualifications |

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Department of Energy 1, Methodology for Counting TQP Personnel and Qualifications FTCP-08-001, Methodology for Counting TQP Personnel and Qualifications FTCP Issue Paper: FTCP-08-001 Approved by FTCP, July 28, 2008 Conference Call FTCP-08-001 TQP Personnel and Qualifications (28.65 KB) More Documents & Publications FTCP-09-001, Safety System Oversight competencies and FAQS Options Technical Qualification Program Self-Assessment Report - Richland Operations Office - 2014 FTCP Conference

  12. U.S. Department of Energy Hydrogen Component and System Qualification

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Workshop - Presentations | Department of Energy U.S. Department of Energy Hydrogen Component and System Qualification Workshop - Presentations U.S. Department of Energy Hydrogen Component and System Qualification Workshop - Presentations These presentations were given at the U.S. Department of Energy Hydrogen Component and System Qualification Workshop held November 4, 2010 in Livermore, CA. Hydrogen Industrial Trucks: Component and System Qualification Workshop Mr. Aaron Harris Nuvera Fuel

  13. Nondestructive Testing Qualification of Main Circulatory Tube Pipes DU 500

    SciTech Connect

    Tabakova, Bojana M.; Tzokov, Petio

    2004-07-01

    The criteria for safe operation of nuclear energetic installations is given a higher priority in the policy of Kozloduy Nuclear Power Plant. An efficient non-destructive inspection is the key point for the safe service. Kozloduy NPP keeps on making investments in equipment and qualification of specialists in this field. The processes of qualification of the NDT components, important for the nuclear and radiation safety, make considerable improvement in Kozloduy NPP, thanks to the accumulated in the years experience in the activities of NDT inspection qualification, and to the help of our partners Serco Assurance and the Institute of Rzes. The results obtained by ultrasonic non-destructive inspection of circulation tube mains DU 500 WWER 440 type are under discussion in this report. (authors)

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

    SciTech Connect

    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

  15. Accelerated Stress Testing, Qualification Testing, HAST, Field Experience

    Office of Energy Efficiency and Renewable Energy (EERE)

    This presentation, which was the opening session of the NREL 2013 Photovoltaic Module Reliability Workshop held on February 26, 2013 in Golden, CO, was presented by John Wohlgemuth. Entitled "Accelerated Stress Testing, Qualification Testing, HAST, Field Experience -- What Do They All Mean?" the presentation details efforts to develop accelerated stress tests beyond the qualification test levels, which are necessary to predict PV module wear-out. The commercial success of PVs is ultimately based on the long-term reliability and safety of the deployed PV modules.

  16. Hanford Waste Vitrification Plant Project Waste Form Qualification Program Plan

    SciTech Connect

    Randklev, E.H.

    1993-06-01

    The US Department of Energy has created a waste acceptance process to help guide the overall program for the disposal of high-level nuclear waste in a federal repository. This Waste Form Qualification Program Plan describes the hierarchy of strategies used by the Hanford Waste Vitrification Plant Project to satisfy the waste form qualification obligations of that waste acceptance process. A description of the functional relationship of the participants contributing to completing this objective is provided. The major activities, products, providers, and associated scheduling for implementing the strategies also are presented.

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

    SciTech Connect

    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.

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

    SciTech Connect

    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)

  19. Functional Area Qualification Standard Job Task Analyses | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Energy Job Task Analyses Functional Area Qualification Standard Job Task Analyses DOE Aviation Manager DOE Aviation Safety Officer Chemical Processing Civil/Structural Engineering Confinement Ventilation and Process Gas Treatment Construction Management Criticality Safety Deactivation and Decommissioning Electrical Systems and Safety Oversight Emergency Management Environmental Compliance Environmental Restoration Facility Representative Fire Protection Engineering General Technical Base

  20. Functional Area Qualification Standards Review Process | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Energy Review Process Functional Area Qualification Standards Review Process Document Available for Download Review Process for Technical Standards (116.38 KB) More Documents & Publications DOE-STD-1176-2004 DOE-TSPP-4-2013, Developing DOE Technical Standards DOE Project Management Risk Committee (PMRC) SOP

  1. Light duty utility arm equipment qualification test procedure

    SciTech Connect

    Kiebel, G.R., Westinghouse Hanford

    1996-07-22

    The Equipment Qualification Test described in this test procedure document is the acceptance test procedure (ATP) for the LDUA Baseline System. It verifies that the equipment is complete and in working order, and demonstrates its readiness for being deployed into an actual underground storage tank.

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

    Directives, Delegations, and Other 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

  3. Decant pump assembly and controls qualification testing - test report

    SciTech Connect

    Staehr, T.W., Westinghouse Hanford

    1996-05-02

    This report summarizes the results of the qualification testing of the supernate decant pump and controls system to be used for in-tank sludge washing in aging waste tank AZ-101. The test was successful and all components are qualified for installation and use in the tank.

  4. Facility Representative Qualification Equivalencies Based on Previous Experience

    Energy.gov [DOE]

    The purpose of this Memorandum is to provide guidance, Attachment 1, to Qualifying Officials (QO) on how to use the cross-walk, Attachment 2, in granting equivalencies to Facility Representative (FR) candidates using the most current FR Functional Area Qualification Standards, DOE-STD-1151-2010.

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

    SciTech Connect

    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

  6. Plutonium metal and oxide container weld development and qualification

    SciTech Connect

    Fernandez, R.; Horrell, D.R.; Hoth, C.W.; Pierce, S.W.; Rink, N.A.; Rivera, Y.M.; Sandoval, V.D.

    1996-01-01

    Welds were qualified for a container system to be used for long-term storage of plutonium metal and oxide. Inner and outer containers are formed of standard tubing with stamped end pieces gas-tungsten-arc (GTA) welded onto both ends. The weld qualification identified GTA parameters to produce a robust weld that meets the requirements of the Department of Energy standard DOE-STD-3013-94, ``Criteria for the Safe Storage of Plutonium Metals and Oxides.``

  7. Civil/Structural Engineering Functional Area Qualification Standard

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    82-2014 September 2014 DOE STANDARD CIVIL/STRUCTURAL ENGINEERING FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A: Approved for public release; distribution is unlimited. DOE-STD-1182-2014 ii This document is available on the Department of Energy Technical Standards Program website at

  8. Functional Area Qualification Standards Template | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Template Functional Area Qualification Standards Template This FAQS template has been derived from DOE FTCP Operational Plans over the years as a "best practice format" after FTCP member-composed teams have provided valuable recommendations on important FAQS elements. It is expected that the FAQS template be followed wherever possible, and only deviated-from for good reason based on that specific FAQS being written/updated. FAQS Template (82.61 KB) More Documents & Publications

  9. NNSA Package Certification Engineer Functional Area Qualification Standard

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    NOT MEASUREMENT SENSITIVE DOE-STD-1026-2016 April 2016 Superseding DOE-STD-1026-2009 DOE STANDARD NNSA PACKAGE CERTIFICATION ENGINEER FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A: Approved for public release; distribution is unlimited DOE-STD-1026-2016 This document is available on the Department of Energy Technical Standards Program Website at

  10. Nuclear Explosive Safety Study Functional Area Qualification Standard

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    i NOT MEASUREMENT SENSITIVE DOE-STD-1185-2007 CHANGE NOTICE No.1 April 2010 DOE STANDARD NUCLEAR EXPLOSIVE SAFETY STUDY FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1185-2007 ii This document is available on the Department of Energy Technical Standards Program Web Site at

  11. Nuclear Explosives Safety Study Functional Area Qualification Standard

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    85-2007 September 2007 DOE STANDARD NUCLEAR EXPLOSIVE SAFETY STUDY FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DRAFT DOE-STD-1185-2007 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DRAFT DOE-STD-1185-2007 iv

  12. High Temperature Materials Interim Data Qualification Report FY 2011

    SciTech Connect

    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.

  13. Safeguards and Security General Technical Base Qualification Standard

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    23-2009 July 2009 DOE STANDARD SAFEGUARDS AND SECURITY GENERAL TECHNICAL BASE QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1123-2009 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-STD-1123-2009 iii APPROVAL The

  14. Safety Software Quality Assurance Functional Area Qualification Standard

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    2-2011 March 2011 DOE STANDARD SAFETY SOFTWARE QUALITY ASSURANCE FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1172-2011 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-STD-1172-2011 INTENTIONALLY BLANK

  15. Technical Qualification Program Reaccreditation Report - Y-12 Site Office |

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Department of Energy Reaccreditation Report - Y-12 Site Office Technical Qualification Program Reaccreditation Report - Y-12 Site Office The accreditation process consists of three distinct activities: (1) a thorough self-evaluation by the organization requesting accreditation; (2) an independent, onsite evaluation by a TQP Accreditation Review Team; and (3) a review by an independent TQP Accreditation Board. This report documents the results of the review of the National Nuclear Security

  16. IWARS Final

    Energy Saver

    Appendices 1. Objective, Scope, and Methodology ......Finally, management felt that an expanded audit scope could have provided a more complete ...

  17. Final Optics

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    final optics Final Optics Schematic layout of NIF's final optics assembly (FOA). The suite of optics for one beamline is on the right. The final optics assemblies (FOAs) are the last element of the main laser system and the first of the target area systems. Each FOA contains four integrated optics modules (IOMs) that incorporate beam conditioning, frequency conversion, focusing, diagnostic sampling, and debris shielding capabilities into a single compact assembly. These optics are shown in the

  18. Qualification of uranium-molybdenum alloy fuel -- conclusions of an international workshop

    SciTech Connect

    Snelgrove, J. L.; Languilee, A.

    2000-02-14

    Thirty-one participants representing 21 reactors, fuel developers, fuel fabricators, and fuel reprocessors in 11 countries discussed the requirements for qualification of U-MO alloy fuel at a workshop held at Argonne National Laboratory on January 17--18, 2000. Consensus was reached that the qualification plans of the US RERTR program and the French U-Mo fuel development program are valid. The items to be addressed during qualification are summarized in the paper.

  19. Model Request for Qualifications to Pre-Qualify Energy Service Companies |

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Department of Energy Request for Qualifications to Pre-Qualify Energy Service Companies Model Request for Qualifications to Pre-Qualify Energy Service Companies This page contains a model Request for Qualifications (RFQ) and associated documents intended for use by a state program to pre-qualify Energy Service Companies (ESCOs) to be available for as-needed Energy Savings Performance Contracting (ESPC) services for state and local governments within that state. The RFQ sets the stage for a

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

    SciTech Connect

    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

  1. DOE-STD-1161-2003; Mechanical Systems Functional Area Qualification...

    Office of Environmental Management (EM)

    STANDARD MECHANICAL SYSTEMS FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 ...

  2. DOE-STD-1173-2003; Criticality Safety Functional Area Qualification...

    Office of Environmental Management (EM)

    STANDARD CRITICALITY SAFETY FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 ...

  3. DOE-STD-1177-2004; Emergency Management Functional Area Qualification...

    Energy Saver

    DOE-STD-1177-2004 January 2004 DOE STANDARD EMERGENCY MANAGEMENT FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy ...

  4. DOE-STD-1170-2003; Electrical Systems Functional Area Qualification...

    Energy.gov [DOE] (indexed site)

    MEASUREMENT SENSITIVE DOE-STD-1170-2003 December 2003 DOE STANDARD ELECTRICAL SYSTEMS FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. ...

  5. DOE-STD-1146-2001; General Technical Base Qualification Standard...

    Office of Environmental Management (EM)

    DOE STANDARD GENERAL TECHNICAL BASE QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 ...

  6. DOE-STD-1174-2003; Radiation Protection Functional Area Qualification...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    STANDARD RADIATION PROTECTION FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 ...

  7. DOE-STD-1160-2003; Occupational Safety Functional Area Qualification...

    Office of Environmental Management (EM)

    STANDARD OCCUPATIONAL SAFETY FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 ...

  8. DOE-STD-1179-2004; Technical Training Functional Area Qualification...

    Energy.gov [DOE] (indexed site)

    STANDARD TECHNICAL TRAINING FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 ...

  9. DOE-STD-1150-2002; Quality Assurance Functional Area Qualification...

    Energy.gov [DOE] (indexed site)

    NOT MEASUREMENT SENSITIVE DOE-STD-1150-2002 April 2002 DOE STANDARD QUALITY ASSURANCE FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. ...

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

    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).

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

    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.

  12. U.S. Department of Energy Component and System Qualification Workshop |

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Department of Energy U.S. Department of Energy Component and System Qualification Workshop U.S. Department of Energy Component and System Qualification Workshop The U.S. Department of Energy (DOE) and Sandia National Laboratories co-hosted the U.S. DOE Component and System Qualification Workshop on November 4, 2010 in Livermore, CA. The goal of the Workshop was to identify key needs, barriers, and actions to facilitate the qualification and listing of hydrogen and fuel cell systems and

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

    SciTech Connect

    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.

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

    SciTech Connect

    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

  15. Final EA

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Lane-Wendson No. 1 Transmission Line Rebuild Project Final Environmental Assessment 1 In cooperation with the Bureau of Land Management Lane-Wendson No. 1 Transmission Line Rebuild Project Final Environmental Assessment DEPARTMENT OF ENERGY Bonneville Power Administration DOE/EA-1952 April 2016 This document is the final Environmental Assessment (EA) for the proposed Lane-Wendson No. 1 Transmission Line Rebuild Project. Bonneville Power Administration (BPA) prepared this document as an

  16. FINAL REPORT

    Office of Scientific and Technical Information (OSTI)

    FINAL REPORT Analytical and Elemental Analysis of Air and Soil Samples Facility and Public ... Information 4 Background 5 Stormwater Pollution 5 Erosion and Sediment Control Workshop ...

  17. Qualification of Three On-line Slurry Monitoring Devices for Application during Waste Retrieval Operations at DOE Sites

    SciTech Connect

    Bontha, Jagannadha R.; Bamberger, Judith A.; Hylton, Tom D.; May, T. H.

    2000-10-18

    Qualification of Three On-line Slurry Monitoring Devices for Application during Waste Retrieval Operations at DOE Sites

  18. FINAL RELEASE

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    RELEASE AWARDEE: ____________________________________________________ The work under Award No. DE-__________________________, dated ______________, between the United States of America (represented by the Department of Energy, National Energy Technology Laboratory, and the undersigned awardee, having been completed and finally accepted , and in consideration of Final Payment thereunder, the United States of America, its officers, agents and employees are hereby released from all liabilities,

  19. NNSA Package Certification Engineer Functional Area Qualification Standard

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    DOE-STD-1026-2009 February 2009 DOE STANDARD NNSA PACKAGE CERTIFICATION ENGINEER FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1026-2009 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-STD-1026-2009 iv

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

    SciTech Connect

    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 300C and 900C. 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.

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

    SciTech Connect

    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.

  2. Resistance Weld Qualification Analysis for Radioactive Waste Canisters

    SciTech Connect

    Gupta, N.K.; Gong, C.

    1995-01-10

    High level radioactive waste canisters are sealed by resistance upset welding to ensure leak tight closures. Resistance welding is fast, uniform, and can be performed remotely to minimize radiation exposure to the operators. Canisters are constructed in accordance with ASME Band PV Code, Section VIII, Division 1, however, the resistance welds are not used in Section VIII. The resistance welds are qualified by analysis using material properties obtained from the test coupons. Burst tests are performed on canister welds to meet ASME Section IX welder qualification requirements. Since burst tests are not used in Section IX for resistance weld qualification, finite element results of canister resistance welds are compared with the finite element analysis results of resistance weld tests in ASME Section IX, QW-196 to establish similarity between the two weld tests. Detailed analyses show that the primary mode of failure in both the tests is shear and, therefore, the use of burst test in place of shear test is acceptable. It is believed that the detailed analyses and results could help in establishing acceptance criteria for resistance upset welding in ASME B&PV Code, Sections VIII, and IX.

  3. Final Report

    SciTech Connect

    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.

  4. Final Report

    SciTech Connect

    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.

  5. Final Report

    SciTech Connect

    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.

  6. Final Agenda

    Office of Environmental Management (EM)

    Abuse Programs at DOE Sites | Department of Energy Federal Register Notice, Amending 10 CFR part 707, Workplace Ssubustance Abuse Programs at DOE Sites Federal Register Notice, Amending 10 CFR part 707, Workplace Ssubustance Abuse Programs at DOE Sites January 23, 2008 The Department of Energy (DOE) today published a final rule to amend the Department's regulations to decrease the random drug testing rate of DOE contractor employees in testing designated positions (TDP). Today's final rule

  7. GAP analysis towards a design qualification standard development for grid-connected photovoltaic inverters.

    SciTech Connect

    Tamizhmani, Govindasamy; Granata, Jennifer E.; Maracas, George; Ayyanar, Raja; Marinella, Matthew; Venkataramanan, Sai Balasubramanian Alampoondi

    2011-06-01

    A dedicated design qualification standard for PV inverters does not exist. Development of a well-accepted design qualification standard, specifically for PV inverters will significantly improve the reliability and performance of inverters. The existing standards for PV inverters such as ANSI/UL 1741 and IEC 62109-1 primarily focus on safety of PV inverters. The IEC 62093 discusses inverter qualification but it includes all the BOS components. There are other general standards for distributed generators including the IEEE 1547 series of standards which cover major concerns like utility integration but they are not dedicated to PV inverters and are not written from a design qualification point of view. In this paper some of the potential requirements for a design qualification standard for PV inverters are addressed. The missing links in existing PV inverter related standards are identified and with the IEC 62093 as a guideline, the possible inclusions in the framework for a dedicated design qualification standard of PV inverter are discussed. Some of the key missing links are related to electric stress tests. Hence, a method to adapt the existing surge withstand test standards for use in design qualification standard of PV inverter is presented.

  8. Hanford Tank Waste Treatment and Immobilization Plant (WTP) Waste Feed Qualification Program Development Approach - 13114

    SciTech Connect

    Markillie, Jeffrey R.; Arakali, Aruna V.; Benson, Peter A.; Halverson, Thomas G.; Adamson, Duane J.; Herman, Connie C.; Peeler, David K.

    2013-07-01

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is a nuclear waste treatment facility being designed and constructed for the U.S. Department of Energy by Bechtel National, Inc. and subcontractor URS Corporation (under contract DE-AC27-01RV14136 [1]) to process and vitrify radioactive waste that is currently stored in underground tanks at the Hanford Site. A wide range of planning is in progress to prepare for safe start-up, commissioning, and operation. The waste feed qualification program is being developed to protect the WTP design, safety basis, and technical basis by assuring acceptance requirements can be met before the transfer of waste. The WTP Project has partnered with Savannah River National Laboratory to develop the waste feed qualification program. The results of waste feed qualification activities will be implemented using a batch processing methodology, and will establish an acceptable range of operator controllable parameters needed to treat the staged waste. Waste feed qualification program development is being implemented in three separate phases. Phase 1 required identification of analytical methods and gaps. This activity has been completed, and provides the foundation for a technically defensible approach for waste feed qualification. Phase 2 of the program development is in progress. The activities in this phase include the closure of analytical methodology gaps identified during Phase 1, design and fabrication of laboratory-scale test apparatus, and determination of the waste feed qualification sample volume. Phase 3 will demonstrate waste feed qualification testing in support of Cold Commissioning. (authors)

  9. U.S. Commits $14 million to U.S. - Ukraine Nuclear Fuel Qualification

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Project | Department of Energy Commits $14 million to U.S. - Ukraine Nuclear Fuel Qualification Project U.S. Commits $14 million to U.S. - Ukraine Nuclear Fuel Qualification Project March 15, 2007 - 10:55am Addthis KYIV, Ukraine - U.S. Department of Energy Deputy Secretary Clay Sell today announced that the United States will invest $14 million to provide 42 nuclear fuel assemblies to the South Ukraine Nuclear Power Plant under the U.S.-Ukraine Nuclear Fuel Qualification Project (UNFQP). In

  10. EDS V25 containment vessel explosive qualification test report.

    SciTech Connect

    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.

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

    SciTech Connect

    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.

  12. Technical Qualification Program Self-Assessment Report- Y-12 Site Office- 2010

    Office of Energy Efficiency and Renewable Energy (EERE)

    The National Nuclear Security Administration Y-12 Site Office (YSO) has successfully implemented a Technical Qualification Program (YSO TQP) that produces highly qualified, technical individuals to execute oversight of site activities and support the site missions.

  13. CRAD, NNSA- Federal Employee Training and Qualification Program (FED T&Q)

    Office of Energy Efficiency and Renewable Energy (EERE)

    CRAD for Federal Employee Training and Qualification Program (FED T&Q). Criteria Review and Approach Documents (CRADs) that can be used to conduct a well-organized and thorough assessment of elements of safety and health programs.

  14. H.A.R. 13-281 - Rules Governing Professional Qualifications ...

    OpenEI (Open Energy Information) [EERE & EIA]

    search OpenEI Reference LibraryAdd to library Legal Document- RegulationRegulation: H.A.R. 13-281 - Rules Governing Professional QualificationsLegal Published NA Year Signed or...

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

    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.

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

    Energy.gov [DOE]

    This Chief of Nuclear Safety (CNS) Report was prepared to summarize the results of the July 2013 CNS self-assessment of the Senior Technical Safety Manager Qualification Program.

  17. Technical Qualification Program Self-Assessment Report- Savannah River Site Office- 2011

    Energy.gov [DOE]

    This self assessment evaluates the effective implementation of the Technical Qualification Programs (TQP). The Federal Technical Capability Panel (FTCP) also reviews the results of the TQP self-assessments and determines if further action is necessary on a Departmental level.

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

    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.

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

    SciTech Connect

    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

    Marchant, Gary E.

    2013-04-23

    This is the final report of a two year project entitled "Governing Nanotechnology Risks and Benefits in the Transition to Regulation: Innovative Public and Private Approaches." This project examined the role of new governance or "soft law" mechanisms such as codes of conduct, voluntary programs and partnership agreements to manage the risks of emerging technologies such as nanotechnology. A series of published or in publication papers and book chapters are attached.

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

    SciTech Connect

    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.

  2. Final Report

    SciTech Connect

    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.

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

    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,...

  4. Initial results of strand produced in Phase 2 of the SSCL Vendor Qualification Program

    SciTech Connect

    Erdmann, M.; Capone, D. II; Coleman, S.; Jones, B.; Seuntjens, J.

    1993-05-01

    In 1991, the Superconducting Super Collider Laboratory (SSCL) instituted a program to qualify specific superconductor manufacturers for production of cable acceptable for use in both Collider Dipole (CDM) and Quadrupole (CQM) magnets. The SSCL Vendor Qualification Program (VQP) was designed with two Phases. Phase 1 was divided into two additional phases, 1A and 1B, which ran concurrently. In Phase 1B, each vendor was directed to manufacture roughly 3000 kg of cable using a ``baseline`` process. The baseline process was agreed to by both the SSCL and the vendor at the beginning of the VQP. In this phase, process control was closely monitored with the use of statistical methods and each vendor was graded based on these results. Phase 1A, known as the R&D phase, was developed to allow each vendor an opportunity to optimize and improve on their baseline process in terms of both cost and manufacturability. In this phase, multifilament billets were designed to explore several key variables such as alternate alloy sources, process modifications and improved billet designs. At the end of Phase 1, the results from both 1A and 1B were evaluated at a review between the SSCL and each vendor, and a final Phase 2 process was generated and fixed using the best results. In Phase 2, each vendor is required to manufacture roughly 6000 kg of superconducting cable under a firm fixed price contract which can then be used to create an accurate price estimate for competitive bidding on the full rate production CDM and CQM contracts. At the end of Phase 2, each vendor must meet the minimum requirements outlined in the contract to become a qualified superconducting cable supplier. For one requirement, critical process variables identified by the SSCL Conductor Department at the beginning of the VQP will be evaluated to determine the quality and uniformity of the material produced during Phase 2 of the program.

  5. Final Report

    SciTech Connect

    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).

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

    SciTech Connect

    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.

  7. DOE handbook: Guide to good practices for training and qualification of chemical operators

    SciTech Connect

    1996-03-01

    The purpose of this Handbook is to provide contractor training organizations with information that can be used as a reference to refine existing chemical operator training programs, or develop new training programs where no program exists. This guide, used in conjunction with facility-specific job analyses, will provide a framework for training and qualification programs for chemical operators at DOE reactor and nonreactor facilities. Recommendations for qualification are made in four areas: education, experience, physical attributes, and training. Contents include: initial qualification; administrative training; industrial safety training; specialized skills training; on-the-job training; trainee evaluation; continuing training; training effectiveness evaluation; and program records. Two appendices describe Fundamentals training and Process operations. This handbook covers chemical operators in transportation of fuels and wastes, spent fuel receiving and storage, fuel disassembly, fuel reprocessing, and both liquid and solid low-level waste processing.

  8. Non-destructive qualification tests for ITER cryogenic axial insulating breaks

    SciTech Connect

    Kosek, Jacek; Lopez, Roberto; Tommasini, Davide; Rodriguez-Mateos, Felix

    2014-01-29

    In the ITER superconducting magnets the dielectric separation between the CICC (Cable-In-Conduit Conductors) and the helium supply pipes is made through the so-called insulating breaks (IB). These devices shall provide the required dielectric insulation at a 30 kV level under different types of stresses and constraints: thermal, mechanical, dielectric and ionizing radiations. As part of the R and D program, the ITER Organization launched contracts with industrial companies aimed at the qualification of the manufacturing techniques. After reviewing the main functional aspects, this paper describes and discusses the protocol established for non-destructive qualification tests of the prototypes.

  9. Technical Qualification Program Self-Assessment Report - Los Alamos Field

    Office of Environmental Management (EM)

    Transportation, Aging and Disposal Canister Systems | Department of Energy Task Order 18 Updated Final Report: Generic Design for Small Standardized Transportation, Aging and Disposal Canister Systems Task Order 18 Updated Final Report: Generic Design for Small Standardized Transportation, Aging and Disposal Canister Systems Per the requirements of the Task Order 18: Generic Design for Small Standardized Transportation, Aging, and Disposal Canister Systems, Statement of Work (SOW),

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

    SciTech Connect

    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

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

    SciTech Connect

    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

  12. Technical Qualification Program Self-Assessment Report- Nevada Site Office- 2009

    Energy.gov [DOE]

    An accreditation assessment of the National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Technical Qualification Program (TQP) was conducted during the week of October 5-8, 2009. The accreditation of the TQP will enable NSO to demonstrate that they have an effective program in place to ensure the technical competency of the individuals performing these activities.

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

    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.

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

    SciTech Connect

    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.

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

    SciTech Connect

    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.

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

    Directives, Delegations, and Other 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.

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

    Office of Energy Efficiency and Renewable Energy (EERE)

    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.

  18. Technical Qualification Program Self-Assessment Report- Los Alamos Field Office- FY14

    Energy.gov [DOE]

    The FY14 self-assessment of the Technical Qualifications Program and Federal Technical Capabilities Program was conducted to provide Los Alamos Field Office (NA-LA) management specific information related to effectiveness of the documentation and implementation of these programs.

  19. Technical Qualification Program and FTCP Self-Assessment Report- Idaho Operations Office- 2015

    Energy.gov [DOE]

    The Department of Energy Idaho Operations Office conducted a management self-assessment of the DOE-ID Technical Qualification Program and Federal Technical Capability Program from October 26 thru December 15, 2015. The management self-assessment was conducted by the Assistant Manager, Nuclear and Safety Performance (also the Federal Technical Capabilities Panel Agent) and a Facility Representative.

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

    Directives, Delegations, and Other 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.

  1. An in progress experience on seismic qualification of gas insulated substations

    SciTech Connect

    Bargigia, A. ); Salvetti, M.; Vallino, M. )

    1993-01-01

    The paper presents ENEL's approach for the seismic qualification of standardized GIS. Starting from experimental and analytical activities performed on standardized metal-enclosed primary distribution substations (170 kV), a methodology suitable also for lower (MV) and higher (EHV and UHV) voltage ranges has been defined, taking into account the site characteristics in terms of seismic severity and soil properties.

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

    SciTech Connect

    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

  3. Qualification of Innovative High Level Waste Pipeline Unplugging Technologies

    SciTech Connect

    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

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

    SciTech Connect

    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

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

    SciTech Connect

    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

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

    SciTech Connect

    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

  7. SLUDGE BATCH 4 FOLLOW-UP QUALIFICATION STUDIES TO EVALUATE HYDROGEN GENERATION

    SciTech Connect

    Pareizs, J; David Koopman, D; Dan Lambert, D; Cj Bannochie, C

    2007-08-23

    Follow-up testing was conducted to better understand the excessive hydrogen generation seen in the initial Sludge Batch 4 (SB4) qualification Sludge Receipt and Adjustment Tank/Slurry Mix Evaporator (SRAT/SME) simulation in the Savannah River National Laboratory (SRNL) Shielded Cells. This effort included both radioactive and simulant work. The initial SB4 qualification test produced 0.59 lbs/hr hydrogen in the SRAT, which was just below the DWPF SRAT limit of 0.65 lbs/hr, and the test produced over 0.5 lbs/hr hydrogen in the SME cycle on two separate occasions, which were over the DWPF SME limit of 0.223 lbs/hr.

  8. Regulatory Guide 1. 8: Qualification and training of personnel for nuclear power plants

    SciTech Connect

    Not Available

    1987-04-01

    Paragraph 50.34(b)(6)(i) of 10 CFR Part 50, ''Domestic Licensing of Production and Utilization Facilities,'' requires that an application for a license to operate a nuclear power plant include information concerning organizational structure, personnel qualifications, and related matters. Subpart D, ''Applications,'' of 10 CFR Part 55, ''Operators' Licenses,'' requires that operator license applications include information concerning an individual's education and experience and related matters. This regulatory guide describes a method acceptable to the NRC staff for complying with those portions of the Commission's regulations with regard to the training and qualifications of nuclear power plant personnel. Personnel of test, training, research, and mobile reactors are not covered by this regulatory guide.

  9. Reliability Testing Beyond Qualification as a Key Component in Photovoltaic's Progress Toward Grid Parity: Preprint

    SciTech Connect

    Wohlgemuth, J. H.; Kurtz, S.

    2011-02-01

    This paper discusses why it is necessary for new lower cost PV modules to be tested using a reliability test sequence that goes beyond the Qualification test sequence now utilized for modules. Today most PV modules are warranted for 25 years, but the Qualification Test Sequence does not test for 25-year life. There is no accepted test protocol to validate a 25-year lifetime. This paper recommends the use of long term accelerated testing to compare now designs directly with older designs that have achieved long lifetimes in outdoor exposure. If the new designs do as well or better than the older ones, then it is likely that they will survive an equivalent length of time in the field.

  10. Results of a literature review on the environmental qualification of low-voltage electric cables

    SciTech Connect

    Lofaro, R.; Lee, B.; Villaran, M.; Gleason, J.; Aggarwal, S.

    1995-12-31

    In the design of nuclear power plants in the US, safety-related electric equipment must be qualified to provide reasonable assurance it can withstand the effects of a design basis event (DBE) and still be able to perform its prescribed safety function, even if the accident were to occur at the end of its service life. The requirement for environmental qualification (EQ) originates from the General Design Criteria in the Code of Federal Regulations, Title 10, Part 50 (10 CFR 50). The acceptable method of performing the qualification of this equipment has evolved over the years, starting with the NRC Division of Operating Reactors (DOR) Guidelines, which were issued in Bulletin 79--01B, and NUREG-0588 requirements and ending with the current EQ Rule, 10 CFR 50.49. While the EQ methods described in these documents have the same overall objective, there are some notable differences for which a clear technical basis has not been established. One difference is the preaging requirement for equipment prior to LOCA testing. In addition, specific issues related to current EQ practices have been raised by the US NRC which need to be addressed. These issues, which are discussed in detail later in this paper, are related to the sources of conservatism and uncertainty in IEEE Standard 323--1974, which is the qualification standard currently endorsed by the NRC. To address these issues, the NRC Office of Nuclear Reactor Regulation (NRR) implemented a Task Action Plan (TAP), and the Office of Nuclear Reactor Research (RES) initiated a complementary research program. The current focus of this program is on the qualification of low-voltage instrumentation and control cables. These cables were selected since they are not typically replaced on a routine basis, and their degradation could impact plant safety.

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

    SciTech Connect

    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.

  12. Technical Qualification Program Self-Assessment Report- Los Alamos Site Office- 2013

    Energy.gov [DOE]

    This self-assessment of the Technical Qualifications and Federal Technical Capability program was conducted to provide Los Alamos Field Office (LAFO) management specific information related to effectiveness of the documentation and implementation of these programs. The conclusion of this assessment is that the areas assessed herein are compliant with the requirements, and that implementation of the requirements has been effective at this Field Office.

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

    SciTech Connect

    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. B-Plant D-Filter detector system qualification test report

    SciTech Connect

    Ritter, G.A., Westinghouse Hanford

    1996-08-23

    This report summarizes the results of qualification testing of the B Plant D-Filter Detector System. The purpose of this test was to verify that the system meets the performance requirements and that the unit is ready for field deployment. Testing was performed in the test pit in the 306E Facility. This detector system will be deployed in the B Plant D-Filter to measure beta/gamma dose rates from the filter bank.

  15. Strategy/Approach for Qualification of Nuclear Components Produced Via AM„Project Objectives

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Electric Power Research Institute, Inc. All rights reserved. David W. Gandy, FASM Nuclear Materials Electric Power Research Institute Davgandy@epri.com AMM Workshop October 17-18, 2016 Strategy/Approach for Qualification of Nuclear Components Produced Via AM 2 © 2016 Electric Power Research Institute, Inc. All rights reserved. Introduction  ASME, NRC, and industry are struggling to identify strategy/approach for nuclear quality components manufactured by AM.  Current approach requires

  16. Technical Qualification Program Self-Assessment Report - NA-SH - 2013 |

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Department of Energy NA-SH - 2013 Technical Qualification Program Self-Assessment Report - NA-SH - 2013 DOE Federal Technical Capability Panel provides the requirements for the recruitment, deployment, development, and retention of federal personnel with demonstrated technical capability to safely accomplish the Department's missions and responsibilities. This Program applies to the National Nuclear Security Administration (NNSA) Headquarters (HQ) and Field organizations that have safety

  17. General Technical Base Qualification Standard (DOE Defense Nuclear Facilities Technical Personnel)

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    DOE-STD-1146-2007 December 2007 DOE STANDARD GENERAL TECHNICAL BASE QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1146-2007 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-STD-1146-2007 iv INTENTIONALLY BLANK

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

    SciTech Connect

    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.

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

    SciTech Connect

    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.

  20. Concentrator Photovoltaic Qualification Standards for Systems Using Refractive and Reflective Optics: Preprint

    SciTech Connect

    McConnell, R.; Ji, L.; Lasich, J.; Mansfield, R.

    2004-06-01

    This paper describes a proposed international qualification standard for photovoltaic (PV) systems generating electricity from concentrated sunlight. The standard's purpose is to provide stress tests and procedures to identify any component weaknesses in a system. If no weaknesses are identified during qualification, both the manufacturer and the customer can expect a more reliable product. In 2002, we began developing the standard, under the auspices of the International Electrotechnical Commission (IEC), that would describe testing procedures for concentrator PV systems using reflecting (mirrors) or refractive (lenses) optics for focusing sunlight onto solar cells. The initial draft of the IEC standard was based on the first concentrator PV qualification standard published by the Institute of Electrical and Electronics Engineers (IEEE) in the United States in 2001. Well-developed U.S. concentrator technologies use refractive optics, and the IEEE standard needed improvement for testing systems with reflective optics. Furthermore, with record III-V solar cell efficiencies above 37%, concentrator PV developers around the world would like to incorporate such cells into their next generation of technologies. The paper will highlight significant differences between the proposed IEC standard and the earlier IEEE standard.

  1. Full Final Report

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    REPOR FULL FINAL REPOR T T SECTION III SECTION III FULL FINAL REPORT SECTION III Individual Project Summaries Table of Contents Algal Biology ..................................................................................................3 Cultivation ...................................................................................................41 Harvesting and Extraction .............................................................................65 Fuel Conversion

  2. Final EIS Volume 3

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Volume 3 Final Environmental Impact Statement for Decommissioning and/or Long-Term Stewardship at the West Valley Demonstration Project and Western New York Nuclear Service Center DOE/EIS-0226 January 2010 The West Valley Site Comment Response Document Final Environmental Impact Statement for AVAILABILITY OF THE FINAL EIS FOR DECOMMISSIONING AND/OR LONG- TERM STEWARDSHIP AT THE WEST VALLEY DEMONSTRATION PROJECT AND WESTERN NEW YORK NUCLEAR SERVICE CENTER For further information on this Final

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

    SciTech Connect

    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

  4. Standard for the qualification of high capacity fossil fuel fired plant operators

    SciTech Connect

    Axtman, W.

    1996-12-31

    The American Society of Mechanical Engineers, at the request of the U.S. Environmental Protection Agency (EPA) and, in recognition of the needs and benefits associated with standard qualifications of operators of high capacity fossil fuel fired plants, established the Qualifications of High Capacity Fossil Fuel Fired Operator (QFO) Committee in 1994. The purpose of the QFO Committee is to develop and maintain such a standard for operators. This standard includes qualifications, duties, responsibilities and the certification requirements for operators as appropriate to The Clean Air Act as amended in 1990 for fossil fuel fired plants with inputs equal to or greater than 10,000 Btu/hr. This Standard does not cover the certification or validation of fossil plant operating procedures, operating practices, facility performance, nor compliance with any particular permit requirement. This standard recognizes the titles or positions to which any particular fossil plant operator may apply, will vary within a facility. Therefore, this standard does not attempt to identify the individual who is required to obtain certification in any class designation. The fossil plant owner is urged to contact the local jurisdiction in which the fossil plant is located in this regard. This standard does not in itself require certification but rather it serves as a means for complying with federal, state, and local regulations which require operators of fossil fuel fired boilers with inputs equal to or greater than 10,000,000 But/hr to be certified. Safety codes and standards are intended to enhance public health and safety. Revisions to this Standard result from committee considerations of factors such as technological advances, new data, and changing environmental and industry needs. Revisions do not imply that previous editions of this standard were inadequate.

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

    SciTech Connect

    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.

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

    SciTech Connect

    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.

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

    SciTech Connect

    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.

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

    SciTech Connect

    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.

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

    SciTech Connect

    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.

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

    SciTech Connect

    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.

  11. Quality Assurance Program Plan for AGR Fuel Development and Qualification Program

    SciTech Connect

    W. Ken Sowder

    2004-02-01

    Quality Assurance Plan (QPP) is to document the Idaho National Engineering and Environmental Laboratory (INEEL) Management and Operating (M&O) Contractor’s quality assurance program for AGR Fuel Development and Qualification activities, which is under the control of the INEEL. The QPP is an integral part of the Gen IV Program Execution Plan (PEP) and establishes the set of management controls for those systems, structures and components (SSCs) and related quality affecting activities, necessary to provide adequate confidence that items will perform satisfactorily in service.

  12. West Valley glass product qualification durability studies, FY 1987--1988: Effects of composition, redox state, thermal history, and groundwater

    SciTech Connect

    Reimus, M.A.H.; Piepel, G.F.; Mellinger, G.B.; Bunnell, L.R.

    1988-11-01

    The product qualification subtask of the West Valley Support Task (WVST) at Pacific Northwest Laboratory (PNL) provides support for the waste form qualification efforts at West Valley Nuclear Services Co. Testing is being conducted to determine waste form chemical durability in support of these efforts. The effects of composition, ferrous/ferric ratio (redox state), thermal history, and groundwater are being investigated. Glasses were tested using modified Materials Characterization Center (MCC) -3 and MCC-1 test methods. Results obtained in fiscal years (FY) 1987 and 1988 are presented here. 13 refs., 27 figs., 36 tabs.

  13. Final Project Report

    SciTech Connect

    Wang, Qiang; Dandy, David S.

    2015-05-15

    This is the final technical report of the DOE project DE-FG02-07ER46448 awarded to Colorado State University.

  14. National Science Bowl Finals

    ScienceCinema

    None

    2016-07-12

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

  15. DOE Final Report

    SciTech Connect

    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.

  16. Significance of in-structure generated motion in seismic qualification electrical devices

    SciTech Connect

    Thinnes, G.; Glozman, V.

    1988-07-01

    The Idaho National Engineering Laboratory (INEL) has been conducting a research study to assist the United States Nuclear Regulatory Commission (USNRC) in determining susceptibility of electrical devices to in-structure generated motion sometimes present in electrical cabinets. In Phase I of this study, a survey of past seismic qualification tests conducted at Wyle Laboratories on various electrical and control equipment housed in nuclear grade cabinets was taken to identify components which experienced a rattling environment. The INEL has used several different methods to reduce that data and has determined the existence of a number of device anomalies in the presence of high frequency cabinet response to earthquake-type excitation motion. However, causality between the high frequency content and the malfunctions could not be conclusively confirmed. Phase II of the study consisted of shake table testing for the most prevalent malfunction discovered in the survey, relay chatter, with excitation frequency content in the seismic range and higher. This report will document the results of Phase I and II of the study. Insight into the susceptibility of electrical devices to rattling and characterization of relay chatter mechanisms offers guidance in addressing rattling effects during qualifications.

  17. Characterization of the SRNL-Washed tank 51 sludge batch 9 qualification sample

    SciTech Connect

    Pareizs, J. M.

    2016-01-01

    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) sent SRNL a 3-L sample of Tank 51H slurry to be characterized, washed, and then used in a lab-scale demonstration of the DWPF flowsheet (after combining with Tank 40H sludge). SRNL has washed the Tank 51H sample per the Tank Farm washing strategy as of October 20, 2015. A part of the qualification process is extensive radionuclide and chemical characterization of the SRNL-washed Tank 51H slurry. This report documents the chemical characterization of the washed slurry; radiological characterization is in progress and will be documented in a separate report. The analytical results of this characterization are comparable to the Tank Farm projections. Therefore, it is recommended that SRNL use this washed slurry for the ongoing SB9 qualification activities.

  18. Examination of a Junction-Box Adhesion Test for Use in Photovoltaic Module Qualification (Presentation)

    SciTech Connect

    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.

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

    SciTech Connect

    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.

  20. Guide to good practices for the selection, training, and qualification of shift technical advisors

    SciTech Connect

    1993-02-01

    The DOE Guide to Good Practices For the Selection, Training, and Qualification of Shift Technical Advisors can be used by any DOE nuclear facility that has implemented the shift technical advisor (STA) position. DOE Order 5480.20A, Personnel Selection, Qualification and Training Requirements for DOE Nuclear Facilities, states that only Category A reactors must have a shift technical advisor. However, many DOE nuclear facilities have implemented the shift technical advisor position to provide independent on-shift technical advice and counsel to the shift operating personnel to help determine cause and mitigation of facility accidents. Those DOE nuclear facilities that have implemented or are going to implement the shift technical advisor position will find this guide useful. This guide addresses areas that may be covered by other training programs. In these cases, it is unnecessary (and undesirable) to duplicate these areas in the STA training program as long as the specific skills and knowledge essential for STAs are addressed. The guide is based on the premise that the trainee has not completed any facility-specific training other than general employee training.

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

    SciTech Connect

    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.

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

    SciTech Connect

    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

  3. Microsoft Word - Merit Review Guide FINAL JULY 2013

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    qualifications when selecting reviewers: 1. The individual's scientific or technical education and experience (at least 5 years of experience in a relevant field); 2. The...

  4. Microsoft Word - TQP 1 31 Final w signatures.docx

    Office of Environmental Management (EM)

    Los Alamos Site Office Technical Qualification Program Self-Assessment Report U.S. Department of Energy National Nuclear Security Administration January 10-13, 2011 This page ...

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

    SciTech Connect

    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

  6. Final EIS Volume 2

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Volume 2 Final Environmental Impact Statement for Decommissioning and/or Long-Term Stewardship at the West Valley Demonstration Project and Western New York Nuclear Service Center DOE/EIS-0226 January 2010 The West Valley Site (Appendices A through R) AVAILABILITY OF THE FINAL EIS FOR DECOMMISSIONING AND/OR LONG- TERM STEWARDSHIP AT THE WEST VALLEY DEMONSTRATION PROJECT AND WESTERN NEW YORK NUCLEAR SERVICE CENTER For further information on this Final EIS, or to request a copy of the EIS or

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

    SciTech Connect

    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

  8. Aurora final report

    SciTech Connect

    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)

  9. CFC Charity Fair Finale

    Energy.gov [DOE]

    Finish out the 2012 CFC with the Charity Fair Finale! Buy cookies, participate in a putt-putt golf game, eat some popcorn, and meet and talk with CFC charity representatives.

  10. CX-100 Final Report

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    SAND2008-4648 Unlimited Release Printed July 2008 Blade System Design Studies Phase II: Final Project Report Derek S. Berry TPI Composites, Inc. 373 Market Street Warren, RI 02885...

  11. Microsoft Word - Final Report

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    J. Michael Doster NCSU September 30, 2013 CASL-8-2013-0201-000 Final Report L3.THM.CFD.P7.07 Dr. J. Michael Doster Nuclear Engineering Department North Carolina State University ...

  12. Final EIS Available

    Energy.gov [DOE]

    DOE has published a Final Environmental Impact Statement (EIS) that considers all timely public comments on the Draft EIS and identifies DOE’s preferred project alternative(s). The U.S....

  13. Final focus test beam

    SciTech Connect

    Not Available

    1991-03-01

    This report discusses the following: the Final Focus Test Beam Project; optical design; magnets; instrumentation; magnetic measurement and BPM calibration; mechanical alignment and stabilization; vacuum system; power supplies; control system; radiation shielding and personnel protection; infrastructure; and administration.

  14. Blackout Final Implementation Report

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Final Report on the Implementation of the Task Force Recommendations U.S.-Canada Power System Outage Task Force Natural Resources Canada U.S. Department of Energy September 2006 Final Report on the Implementation of the Task Force Recommendations U.S.-Canada Power System Outage Task Force September 2006 Natural Resources Canada U.S. Department of Energy Acknowledgments This document was prepared by staff of Natural Resources Canada and the U.S. Department of Energy. The principal contributors

  15. Final - Gasbuggy S

    Office of Legacy Management (LM)

    Gasbuggy S i t e Environmental Management End State Vision - January 2005 U.S. DEPARTMENT OF ENERGY Gasbuggy Site ENVIRONMENTAL MANAGEMENT END STATE VISION Final Final - Gasbuggy Site Environmental Management End State Vhion - fanuaty 2005 Executive Summary The Environmental Management End State Vision is to be used as the primary tool for communicating the individual site end state to the involved parties (e.g., U.S. Department of Energy [DOE], regulators, public stakeholders, Tribal Nations).

  16. Final Environmental Impact Statement

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    EIS - 0097-F c f ` f= �c J m s= Final Environmental Impact Statement BONNEVILLE POWER ADMINISTRATION TRANSMISSION FACILITIES VEGETATION MANAGEMENT PROGRAM U.S. Department of Energy August 1983 Appendices albLbfp= J MMVTJc= Responsible Official: tfiif^j= ^K= s^rde^k= Assistant Secretary for Environmental Protection. Safety, and Emergency Prepafedness Final Environmental Impact Statement BONNEVILLE POWER ADM IN ISTRA TION TRANSMISSION FACILITIES VEGETATION MANAGEMENT PROGRAM U.S. Department of

  17. RPSEA FINAL TECHNICAL REPORT

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    RPSEA FINAL TECHNICAL REPORT 12122.52.FINAL Hugh Daigle, Nicholas W. Hayman, Kyle Spikes, Julia Gale, Peter Eichhubl, Kitty L. Milliken University of Texas at Austin Connectivity between Fractures and Pores in Hydrocarbon-Rich Mudrocks Contract Number 12122-52 June 24, 2016 Principal Investigator: Hugh Daigle Assistant Professor Department of Petroleum and Geosystems Engineering University of Texas at Austin 200 E Dean Keeton St., Stop C0300, Austin, TX 78712-1585 2 LEGAL NOTICE This report was

  18. Caspary Thesis Final

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    DENSITY AND BETA LIMITS IN THE MADISON SYMMETRIC TORUS REVERSED-FIELD PINCH by KYLE JONATHAN CASPARY A dissertation submitted in partial fulfillment of the requirements for the degree of Doctor of Philosophy (PHYSICS) at the UNIVERSITY OF WISCONSIN-MADISON 2014 Date of final oral examination: March 24th, 2014 The dissertation is under review by the following members of the Final Oral Committee: Brett Chapman, Senior Scientist, Physics John Sarff, Professor, Physics Paul Terry, Professor, Physics

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

    SciTech Connect

    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.

  20. Final Technical Report

    SciTech Connect

    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.

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

    SciTech Connect

    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

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

    SciTech Connect

    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).

  4. Final Technical Report

    SciTech Connect

    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.

  5. Flatsheet_Final

    Office of Environmental Management (EM)

    Department of Energy First Solar AVSR Solar Ranch Technical Eligibility Re-Evaluation Memo First Solar AVSR Solar Ranch Technical Eligibility Re-Evaluation Memo First_Solar_AVSR_Solar_Ranch_One_Technical_Eligibility_Re-Evaluation.pdf (81.63 KB) More Documents & Publications ANTELOPE VALLEY SOLAR RANCH EA-1826: Final Environmental Assessment REEE Solicitation Public Meeting Presentation Department of Energy

    First Step to Spur U.S. Manufacturing of Small Modular Nuclear Reactors

  6. Final Scientific/Technical Report

    SciTech Connect

    Troxell, W; Batchelor, A

    2012-11-28

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

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

    SciTech Connect

    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).

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

    SciTech Connect

    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).

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

    SciTech Connect

    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.

  10. Sample Results from the Interim Salt Disposition Program Macrobatch 8 Tank 21H Qualification Samples

    SciTech Connect

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

    2015-01-01

    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(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.

  11. Sample results from the Interim Salt Disposition Program Macrobatch 8 Tank 21H qualification samples

    SciTech Connect

    Peters, T. B.; Washington, II, 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(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.

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

    SciTech Connect

    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.

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

    SciTech Connect

    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. Qualification High Voltage Testing of Short Triax HTS Cables in the Laboratory

    SciTech Connect

    James, David Randy; Sauers, Isidor; Ellis, Alvin R; Tuncer, Enis; Gouge, Michael J; Demko, Jonathan A; Duckworth, Robert C; Rey, Christopher M

    2009-01-01

    In order to qualify the electrical insulation design of future HTS cables installed in the electric grid, a number of high voltage qualification tests are generally performed in the laboratory on either single-phase model cables and/or actual three-phase cable samples. Prior to installation of the 200-m Triax HTS cable at the American Electric Power Bixby substation near Columbus, Ohio, in September, 2006, such tests were conducted on both single-phase model cables made at ORNL and tri-axial cable sections cut off from cable made on a production run. The three-phase tri-axial design provides some specific testing challenges since the ground shield and three phases are concentric about a central former with each phase separated by dielectric tape insulation immersed in liquid nitrogen. The samples were successfully tested and qualified for partial discharge inception, AC withstand, and lightning impulse where voltage is applied to one phase with the other phases grounded. In addition one of the phase pairs was tested for dc withstand as a ldquoworst caserdquo scenario to simulate the effect of VLF (Very Low Frequency) tests on the actual cable installed at the Bixby site. The model and prototype cables will be described and the high voltage test results summarized.

  15. Final Technical Report

    SciTech Connect

    Sobecky, Patricia A; Taillefert, Martial

    2013-03-29

    This final technical report describes results and findings from a research project to examine the role of microbial phosphohydrolase enzymes in naturally occurring subsurface microorganisms for the purpose of promoting the immobilization of the radionuclide uranium through the production of insoluble uranium phosphate minerals. The research project investigated the microbial mechanisms and the physical and chemical processes promoting uranium biomineralization and sequestration in oxygenated subsurface soils. Uranium biomineralization under aerobic conditions can provide a secondary biobarrier strategy to immobilize radionuclides should the metal precipitates formed by microbial dissimilatory mechanisms remobilize due to a change in redox state.

  16. Near-Final Agenda

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    09 26 2014 Near-Final Agenda Workshop on Estimating the Benefits and Costs of Distributed Energy Technologies September 30 - October 1, 2014 Washington, DC September 30 - Day One 8:00 a.m. Coffee and Registration 8:30 Welcome and Opening Remarks * Overview and purpose of the workshop o Comments by senior DOE Officials o Q&A (time permitting) * Around-the-room introductions 9:00 Framing the Issues * Three presentations on key issues * Facilitated discussion 10:15 BREAK 10:30 Estimating the

  17. Final Scientific EFNUDAT Workshop

    ScienceCinema

    None

    2016-07-12

    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

  18. Final Progress Report

    SciTech Connect

    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.

  19. Final Scientific EFNUDAT Workshop

    ScienceCinema

    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 facilitiesInternational 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 VlachoudisWorkshop Assistant: Graldine Jean

  20. Final Scientific EFNUDAT Workshop

    ScienceCinema

    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

  1. FINAL/ SCIENTIFIC TECHNICAL REPORT

    SciTech Connect

    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 Americas 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.

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

    SciTech Connect

    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.

  3. NTSF Spring 2010 Final Agenda

    Energy.gov [DOE]

    Final Agenda for the U.S. Department of Energy's National Transportation Stakeholder Forum taking place in Chicago, Illinois.

  4. ESPC ENABLE Final Proposal Requirements

    Energy.gov [DOE]

    Document describes the final proposal requirements for consideration by an energy service company (ESCO) for an agency’s Request for Quote/Notice of Opportunity or final proposal. If selected to perform a site investment grade audit, the ESCO will be required to present the findings from the IGA and a project price to the agency in the form of a final proposal.

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

    SciTech Connect

    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

  6. Proposed Junction-Box Stress Test (Using an Added Weight) for Use During the Module Qualification (Presentation)

    SciTech Connect

    Miller, D. C.; Wohlgemuth, J. H.; Kurtz, S. R.

    2012-02-01

    Engineering robust adhesion of the junction-box (j-box) is a hurdle typically encountered by photovoltaic (PV) module manufacturers during product development. Furthermore, 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 the j-box adhesion system. The details of the proposed test are described, in addition to the preliminary results conducted using representative materials and components.

  7. Final Technical Report

    SciTech Connect

    Aristos Aristidou Natureworks); Robert Kean; Tom Schechinger; Stuart Birrell; Jill Euken

    2007-10-01

    The two main objectives of this project were: 1) to develop and test technologies to harvest, transport, store, and separate corn stover to supply a clean raw material to the bioproducts industry, and 2) engineer fermentation systems to meet performance targets for lactic acid and ethanol manufacturers. Significant progress was made in testing methods to harvest corn stover in a “single pass” harvest mode (collect corn grain and stover at the same time). This is technically feasible on small scale, but additional equipment refinements will be needed to facilitate cost effective harvest on a larger scale. Transportation models were developed, which indicate that at a corn stover yield of 2.8 tons/acre and purchase price of $35/ton stover, it would be unprofitable to transport stover more than about 25 miles; thus suggesting the development of many regional collection centers. Therefore, collection centers should be located within about 30 miles of the farm, to keep transportation costs to an acceptable level. These collection centers could then potentially do some preprocessing (to fractionate or increase bulk density) and/or ship the biomass by rail or barge to the final customers. Wet storage of stover via ensilage was tested, but no clear economic advantages were evident. Wet storage eliminates fire risk, but increases the complexity of component separation and may result in a small loss of carbohydrate content (fermentation potential). A study of possible supplier-producer relationships, concluded that a “quasi-vertical” integration model would be best suited for new bioproducts industries based on stover. In this model, the relationship would involve a multiyear supply contract (processor with purchase guarantees, producer group with supply guarantees). Price will likely be fixed or calculated based on some formula (possibly a cost plus). Initial quality requirements will be specified (but subject to refinement).Producers would invest in harvest

  8. MIST final report

    SciTech Connect

    Gloudemans, J.R. )

    1991-08-01

    The multiloop integral system test (MIST) was part of a multiphase program started in 1983 to address small-break loss-of-coolant accidents (SBLOCAs) specific to Babcock Wilcox-designed plants. MIST was sponsored by the US Nuclear Regulatory Commission, the Babcock Wilcox Owners Group, the Electric Power Research Institute, and Babcock Wilcox. The unique features of the Babcock Wilcox design, specifically the hot leg U-bends and steam generators, prevented the use of existing integral system data or existing integral system facilities to addresss the thermal-hydraulic SBLOCA questions. MIST was specifically designed and constructed for this program, and an existing facility -- the once-through integral system (OTIS) -- was also used. Data from MIST and OTIS are used to benchmark the adequacy of system codes, such as RELAP5 and TRAC, for predicting abnormal plant transients. The MIST program is reported in eleven volumes; Volumes 2 through 8 pertain to groups of Phase 3 tests by type, Volume 9 presents inter-group comparisons. Volume 10 provides comparisons between the RELAP5 MOD2 calculations and MIST observations, and Volume 11 (with addendum) presents the later, Phase 4 tests. This is Volume 1 of the MIST final report, a summary of the entire MIST program. Major topics include: test advisory grop (TAG) issues; facility scaling and design; test matrix; observations; comparisons of RELAP5 calculations to MIST observations; and MIST versus the TAG issues. 11 refs., 29 figs., 9 tabs.

  9. Final Report to DOE

    SciTech Connect

    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.

  10. Final Technical Report

    SciTech Connect

    Velasco, Mayda

    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.

  11. Final Technical Report

    SciTech Connect

    Alexander Fridman

    2005-06-01

    This DOE project DE-FC36-04GO14052 ''Plasma Pilot Plant Test for Treating VOC Emissions from Wood Products Plants'' was conducted by Drexel University in cooperation with Georgia-Pacific (G-P) and Kurchatov Institute (KI). The objective of this project was to test the Plasma Pilot Plant capabilities in wood industry. The final goal of the project was to replace the current state-of-the-art, regenerative thermal oxidation (RTO) technology by Low-Temperature Plasma Technology (LTPT) in paper and wood industry for Volatile Organic Components (VOC) destruction in High Volume Low Concentration (HVLC) vent emissions. MetPro Corporation joined the team as an industrial partner from the environmental control business and a potential leader for commercialization. Concurrent Technology Corporation (CTC) has a separate contract with DOE for this technology evaluation. They prepared questionnaires for comparison of this technology and RTO, and made this comparison. These data are presented in this report along with the description of the technology itself. Experiments with the pilot plant were performed with average plasma power up to 3.6 kW. Different design of the laboratory and pilot plant pulsed coronas, as well as different analytical methods revealed many new peculiarities of the VOC abatement process. The work reported herein describes the experimental results for the VOCs removal efficiency with respect to energy consumption, residence time, water effect and initial concentration.

  12. Tiger LDRD final report

    SciTech Connect

    Steich, D J; Brugger, S T; Kallman, J S; White, D A

    2000-02-01

    This final report describes our efforts on the Three-Dimensional Massively Parallel CEM Technologies LDRD project (97-ERD-009). Significant need exists for more advanced time domain computational electromagnetics modeling. Bookkeeping details and modifying inflexible software constitute a vast majority of the effort required to address such needs. The required effort escalates rapidly as problem complexity increases. For example, hybrid meshes requiring hybrid numerics on massively parallel platforms (MPPs). This project attempts to alleviate the above limitations by investigating flexible abstractions for these numerical algorithms on MPPs using object-oriented methods, providing a programming environment insulating physics from bookkeeping. The three major design iterations during the project, known as TIGER-I to TIGER-III, are discussed. Each version of TIGER is briefly discussed along with lessons learned during the development and implementation. An Application Programming Interface (API) of the object-oriented interface for Tiger-III is included in three appendices. The three appendices contain the Utilities, Entity-Attribute, and Mesh libraries developed during the project. The API libraries represent a snapshot of our latest attempt at insulated the physics from the bookkeeping.

  13. Final Technical Report

    SciTech Connect

    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.

  14. Title XVII Final Rule | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Final Rule Title XVII Final Rule Title XVII Final Rule (107.56 KB) More Documents & Publications Final Rule (December 4, 2009) Notice of Proposed Rulemaking (August 6, 2009) Final Rule (October 23, 2007)

  15. Microsoft Word - GrenadeLaunchers Final Cover.doc

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    U.S. Department of Energy Office of Inspector General Office of Inspections and Special Inquiries Inspection Report 40 MM Grenade Launcher Qualification Requirements at Department of Energy Sites DOE/IG-0806 November 2008 Department of Energy Washington, DC 20585 November 25, 2008 MEMORANDUM FOR FROM: Inspector General SUBJECT: INFORMATION: Inspection Report on "40 mm Grenade Launcher Qualification Requirements at Department of Energy Sites" BACKGROUND The Department of Energy and its

  16. 2016 ASI Annual Review UTK Wood Final

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Annual Review Meeting Development and Demonstration of a Model Based Assessment Process for Qualification of Embedded Digital Devices in Nuclear Power Applications Richard Wood The University of Tennessee NEET Project No.: 15-8097 October 12-13, 2016 2 Project Overview nProject Goal Develop an effective approach to resolve concerns about common-cause failure (CCF) vulnerabilities in embedded digital devices (EDDs) nFocus Address the challenge of establishing high levels of safety and reliability

  17. Microsoft Word - Final 1703 NOPR _supercedes Final rule_ _2_.doc

    Energy Saver

    Energy 1 Million Electric Vehicle Report Final Microsoft Word - 1 Million Electric Vehicle Report Final Microsoft Word - 1 Million Electric Vehicle Report Final (219.14 KB) More Documents & Publications FY 2012 Annual Progress Report for Energy Storage R&D Hybrid Electric Systems Revolution Now: The Future Arrives for Five Clean Energy Technologies-2015 Update

    5 Annual Report I. Basic Information Regarding Report. A. Abel Lopez, Director FOIA/Privacy Act Group, MA-74 Office of the

  18. MTX final report

    SciTech Connect

    Hooper, E.B.; 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.

    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).

  19. FINAL - Signed Report on ARRA Lesson Learned and Action Memo date 11-14-12 (2)FINAL.pdf

    Office of Environmental Management (EM)

    Quality Assurance FAQS Reference Guide - Quality Assurance This reference guide has been developed to address the competency statements in the April 2002 edition of DOE-Standard (STD)-1150-2002, Quality Assurance Functional Area Qualification Standard. Quality Assurance Qualification Standard Reference Guide, July 2012 (1.91 MB) More Documents & Publications Order Module--DOE O 414.1D, QUALITY ASSURANCE DOE Order on Quality Assurance SOPP-43, EM-23 Quality Assurance Oversight Energy

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

    SciTech Connect

    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.

  1. Regulatory analysis for resolution of Unresolved Safety Issue A-46, seismic qualification of equipment in operating plants

    SciTech Connect

    Chang, T.Y.; Anderson, N.R.

    1987-02-01

    The margin of safety provided in existing nuclear power plant equipment to resist seismically induced loads and perform required safety functions may vary considerably, because of significant changes in design criteria and methods for the seismic qualification of equipment over the years. Therefore, the seismic qualification of equipment in operating plants must be reassessed to determine whether requalification is necessary. The objective of technical studies performed under Task Action Plan A-46 was to establish an explicit set of guidelines and acceptance criteria to judge the adequacy of equipment under seismic loading at all operating plants, in lieu of requiring these plants to meet the criteria that are applied to new plants. This report presents the regulatory analysis for Unresolved Safety Issue (USI) A-46. It includes: Statement of the Problem; the Objective of USI A-46; a Summary of A-46 Tasks; a Proposed Implementation Procedure; a Value-Impact Analysis; Application of the Backfit Rule; 10 CFR 50.109; Implementation; and Operating Plants To Be Reviewed to USI A-46 Requirements.

  2. High-flux, high-temperature thermal vacuum qualification testing of a solar receiver aperture shield

    SciTech Connect

    Kerslake, T.W.; Mason, L.S.; Strumpf, H.J.

    1997-12-31

    equilibrium temperature of 2072 K was achieved. The aperture shield sustained no visible damage as a result of the exposures. This paper describes the aperture shield thermal-vacuum qualification test program including the test article, test facility, procedures, data collection, test success criteria, results and conclusions.

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

    SciTech Connect

    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

  4. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    The U.S. Environmental Protection Agency (EPA) is currently working to submit permit ... into Hanford's current permit. The EPA Consent Agreement and Final Order (CAFO) ...

  5. LIVE_NSB_final.wmv

    ScienceCinema

    None

    2016-07-12

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

  6. Microsoft Word - Abengoa Final EA

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    683 FINAL ENVIRONMENTAL ASSESSMENT FOR DEPARTMENT OF ENERGY LOAN GUARANTEE TO ABENGOA SOLAR INC. FOR THE SOLANA THERMAL ELECTRIC POWER PROJECT NEAR GILA BEND, ARIZONA U.S. ...

  7. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    upcoming action and follow-up items. * Attachment 5: Tri-Party Agreement Agency Fiscal Year 2015 Work Plan- RAP-focused Topics1: Transcribed flipcharts Final Meeting...

  8. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    ... administrative controls, worker training, industrial hygiene procedures, occupational medicine programs and oversight 2009-present" Final Meeting Summary Page 4 Health, Safety ...

  9. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    ADVISORY BOARD PUBLIC INVOLVEMENT AND COMMUNICATION COMMITTEE June 7, 2016 Richland, WA ... Final Meeting Summary Page 2 Public Involvement and Communication Committee June 7, 2016 ...

  10. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Committee September 4, 2013 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD PUBLIC INVOLVEMENT & COMMUNICATION COMMITTEE September 4, 2013 Kennewick, WA Topics in this Meeting Summary ...

  11. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    ADVISORY BOARD PUBLIC INVOLVEMENT AND COMMUNICATION COMMITTEE April 12, 2016 Richland, WA ... Final Meeting Summary Page 2 Public Involvement and Communication Committee April 12, 2016 ...

  12. EA-1637: Final Environmental Assessment

    Office of Energy Efficiency and Renewable Energy (EERE)

    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

  13. AlGaN UV LED and Photodiodes Radiation Hardness and Space Qualifications and Their Applications in Space Science and High Energy Density Physics

    SciTech Connect

    Sun, K. X.

    2011-05-31

    This presentation provides an overview of robust, radiation hard AlGaN optoelectronic devices and their applications in space exploration & high energy density physics. Particularly, deep UV LED and deep UV photodiodes are discussed with regard to their applications, radiation hardness and space qualification. AC charge management of UV LED satellite payload instruments, which were to be launched in late 2012, is covered.

  14. Final Technical Report

    SciTech Connect

    Stenzel, Reiner; Urrutia, J. Manuel

    2009-09-08

    emissions are only observed in whistler spheromaks and FRCs but not in mirrors or asymmetric configurations lacking magnetic null lines. The collisionless electron energization in a toroidal null line usually produces non-Maxwellian distributions. Off the null axis electrons gain more perpendicular than parallel energy. Distributions with T{sub {perpendicular}} > T{sub {parallel}} lead to whistler instabilities which have been observed. A whistler spheromak is a source of high-frequency whistler emissions. These are usually small amplitude whistlers propagating in a complicated background magnetic field. The waves are emitted from a moving source. High frequency whistlers propagate faster than the spheromak, thus partly move ahead of it and partly in the reverse direction. In test wave experiments wave growth opposite to the direction of the hot electron flow has been observed, confirming that Doppler-shifted cyclotron resonance instabilities account for the emission process. Propagating whistler mirrors produce no significant instabilities except when they interact with other fields which exhibit null lines. For example, a whistler mirror has been launched against a stationary FRC, resulting in strong FRC heating and whistler instabilities. In the whistler mirror configuration the antenna near-zone field produces a toroidal null line outside the coil which can also become a source for whistler emissions. Finally, nonlinear EMHD research has been extended to initially unmagnetized plasmas where a new nonlinear skin depth has been discovered. When a small-amplitude oscillating magnetic field is applied to a plasma the field penetration is governed by the skin depth, collisional or collisionless depending on frequency, collision frequency and plasma frequency. However, when the magnetic field increases the electrons become magnetized and the field penetration occurs in the whistler mode if the cyclotron frequency exceeds the oscillating frequency. This phenomenon has been

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

    SciTech Connect

    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 UO

  16. Final ECR 2008 Report | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Final ECR 2008 Report Final ECR 2008 Report Final ECR 2008 Report Environmental Conflict Resolution Third Annual Report January 2009 (224.55 KB) More Documents & Publications Environmental Conflict Resolution 2009 ECR FINAL REPORT 2010 test

  17. EIS-0481: Final Programmatic Environmental Impact Statement ...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    1: Final Programmatic Environmental Impact Statement EIS-0481: Final Programmatic Environmental Impact Statement Engineered High Energy Crop Programs Programmatic Environmental ...

  18. Hawaii Clean Energy Final PEIS

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    A 1 2 Public Notices 3 Notices about the Draft Programmatic EIS Appendix A Hawai i Clean Energy Final PEIS A-1 September 2015 DOE/EIS-0459 The following Notice of Availability appeared in the Federal Register on April 18, 2014. Appendix A Hawai i Clean Energy Final PEIS A-2 September 2015 DOE/EIS-0459 Appendix A Hawai i Clean Energy Final PEIS A-3 September 2015 DOE/EIS-0459 DOE-Hawaii placed the following advertisement in The Garden Island on May 5 and 9, 2014. Appendix A Hawai i Clean Energy

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

    SciTech Connect

    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

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

    SciTech Connect

    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.

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

    SciTech Connect

    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.

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

    SciTech Connect

    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.

  3. 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

    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

  4. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    June 18, 2015 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD HEALTH, SAFETY, AND ENVIRONMENTAL PROTECTION COMMITTEE June 18, 2015 Richland, WA Topics in this Meeting Summary Opening ......................................................................................................................................................... 1 Tank Farm Vapors Advice Response ............................................................................................................ 1 Effectiveness of

  5. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    March 15, 2016 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD RIVER AND PLATEAU COMMITTEE March 15, 2016 Richland, WA Topics in this Meeting Summary Opening ......................................................................................................................................................... 1 Environmental Restoration and Disposal Facility Vertical Expansion ......................................................... 2 Committee Business

  6. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    April 26, 2016 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD RIVER AND PLATEAU COMMITTEE April 26, 2016 Richland, WA Topics in this Meeting Summary Opening ......................................................................................................................................................... 1 Update on Plutonium Finishing Plant ........................................................................................................... 1 Leadership Workshop Preparation, FY 2017

  7. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    August 9, 2016 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD RIVER AND PLATEAU COMMITTEE August 9, 2016 Richland, WA Topics in this Meeting Summary Opening ......................................................................................................................................................... 1 PFP Milestone Change .................................................................................................................................. 2 100 D/H Proposed Plan

  8. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    August 10, 2016 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD TANK WASTE COMMITTEE August 10, 2016 Richland, WA Topics in this Meeting Summary Opening ......................................................................................................................................................... 1 Vapors Monitoring Detection Update (Joint w/HSEP) ................................................................................. 2 Tank

  9. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    4, 2016 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD RIVER AND PLATEAU COMMITTEE October 4, 2016 Richland, WA Topics in this Meeting Summary Opening ......................................................................................................................................................... 2 PFP Update ................................................................................................................................................... 2 Groundwater Year-End Update

  10. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    October 5, 2016 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD TANK WASTE COMMITTEE October 5, 2016 Richland, WA Topics in this Meeting Summary Hanford Site Tour (Joint w/HSEP) ............................................................................................................... 2 Opening ......................................................................................................................................................... 2 Tank Farm Update

  11. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Dennis Faulk, U.S. Environmental Protection Agency (EPA), added that the auguring would ... Area will be remediated by March 2016. EPA and Ecology are working to conduct final ...

  12. Final Report: Axion "Roadmap" Workshop

    SciTech Connect

    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.

  13. GUM Analysis for SIMS Isotopic Ratios in BEP0 Graphite Qualification Samples, Round 2

    SciTech Connect

    Gerlach, David C.; Heasler, Patrick G.; Reid, Bruce D.

    2009-01-01

    This report describes GUM calculations for TIMS and SIMS isotopic ratio measurements of reactor graphite samples. These isotopic ratios are used to estimate reactor burn-up, and currently consist of various ratios of U, Pu, and Boron impurities in the graphite samples. The GUM calculation is a propagation of error methodology that assigns uncertainties (in the form of standard error and confidence bound) to the final estimates.

  14. Final 2011 Supplement Analysis of the 2005 Final SWEIS | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration | (NNSA) Final 2011 Supplement Analysis of the 2005 Final SWEIS Final 2011 Supplement Analysis of the 2005 Final Site-wide Environmental Impact Statement for Continued Operation of LLNL The below final SUPPLEMENT ANALYSIS is available for public viewing. Final 2011 SUPPLEMENT ANALYSIS of the 2005 Final Site-wide Environmental Impact Statement for Continued Operation of Lawrence Livermore National Laboratory Below are links to the final comments response and final

  15. Vibration Testing of Dallas/Maxim iButton Temperature Logger, Model DS1999L, for Flight Qualification on Captive Flight Test Unit?B (CFTU-B)

    SciTech Connect

    Jacobson, G; Lavietes, A

    2005-06-20

    This report documents the flight qualification testing of the Dallas/Maxim iButton temperature logger, model DS1922L, for internal mounting to the W80 Air Launched Cruise Missile (ALCM). A single test was performed utilizing a Labworks Inc. LW-140-110 electro-dynamic vibration system in Building 131, Room 2272, at Lawrence Livermore National Laboratory, Livermore, California. Two DS1922L temperature loggers were tested simultaneously, one horizontally and one vertically. The test consisted of random excitation in the vertical axis for 5-hours. The test spectrum used is a shaped random spectrum defined by the Boeing Company for flight qualification of all modifications flown on ALCM flight tests. The spectrum is defined from 10 to 2000 Hz with a 8.52 g RMS magnitude. The spectrum is given in Table 1 and shown graphically in Figure 1.1.

  16. 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

    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.

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

    SciTech Connect

    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

  18. BP-12 Final Models Datasets

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    MB, XLS) Tier 2 Module of RAM RAM Tier 2 Pricing Module (4.8 MB, XLS) Tool Kit Files (TPP) ToolKit v4.8.1 BP-12 Final Studies Release 4-Aug-11 (12.5 MB, XLS) Risk Mod Output...

  19. MINIMARS conceptual design: Final report

    SciTech Connect

    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)

  20. Final Rule (October 23, 2007)

    Energy.gov [DOE]

    Loan Guarantees for Projects That Employ Innovative Technologies; Final Rule: On May 16, 2007, the Department of Energy (DOE or the Department) published a Notice of Proposed Rulemaking and opportunity for comment (NOPR) to establish regulations for the loan guarantee program authorized by Title XVII of the Energy Policy Act of 2005 (Title XVII or the Act).

  1. Development of optimized PPP insulated pipe-cable systems in the commercial voltage range. Final report

    SciTech Connect

    Allam, E.M.; McKean, A.L.

    1992-05-01

    The primary objectives of this project included the development of an alternate domestic source of Paper-Polypropylene-Paper (PPP) laminate and the development of optimized designs for PPP-insulated pipe-type cable systems in the commercial voltage range. The development of a domestic source of PPP laminate was successfully completed. This laminate was utilized throughout the program for fabrication of full-size prototype cables submitted for laboratory qualification tests. Selected cables at rated voltages of 138, 230 and 345kV have been designed, fabricated and subjected to the series of qualification tests leading to full laboratory qualification. An optimized design of 2000 kcmil, 345kV cable insulated with 600 mils of domestic PPP laminate was fabricated and successfully passed all laboratory qualification tests. This cable design was subsequently installed at Waltz Mill to undergo the series of field tests leading to full commercial qualification.

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

    SciTech Connect

    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.

  3. ERDA-1537: Final Environmental Impact Statement | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    ERDA-1537: Final Environmental Impact Statement ERDA-1537: Final Environmental Impact Statement The Department of Energy (DOE) limits electronic access to certain NEPA documents on ...

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

    Office of Environmental Management (EM)

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

  5. Convective Radio Occultations Final Campaign Summary (Technical...

    Office of Scientific and Technical Information (OSTI)

    Convective Radio Occultations Final Campaign Summary Citation Details In-Document Search Title: Convective Radio Occultations Final Campaign Summary Deep convective systems are ...

  6. Expedited technology demonstration project final report: final forms

    SciTech Connect

    Hopper, R W

    1999-05-01

    ETDP Final Forms was an attempt to demonstrate the fabrication and performance of a ceramic waste form immobilizing the hazardous and radioactive elements of the MSO/SR mineral residues. The ceramic material had been developed previously. The fabrication system was constructed and functioned as designed except for the granulator. Fabrication of our particular ceramic, however, proved unsatisfactory. The ceramic material design was therefore changed toward the end of the project, replacing nepheline with zircon as the sink for silica. Preliminary results were encouraging, but more development is needed. Fabrication of the new ceramic requires major changes in the processing: Calcination and granulation would be replaced by spray drying; and sintering would be at higher temperature. The main goal of the project--demonstrating the fabrication and performance of the waste form--was not achieved. This report summarizes Final Forms' activities. The problem of immobilizing the MSO/SR mineral residues is discussed.

  7. Qualification of Daiichi Units 1, 2, and 3 Data for Severe Accident Evaluations - Process and Illustrative Examples from Prior TMI-2 Evaluations

    SciTech Connect

    Rempe, Joy Lynn; Knudson, Darrell Lee

    2014-09-01

    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. As part of a program initiated in 2012 by the Department of Energy Office of Nuclear Energy (DOE-NE), a review was completed to gain insights from prior TMI-2 sensor survivability and data qualification efforts. This initial review focused on the set of sensors deemed most important by post-TMI-2 instrumentation evaluation programs. 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. In addition, prior efforts focused on sensors providing data required for subsequent forensic evaluations and accident simulations. To encourage the potential for similar activities to be completed for qualifying data from Daiichi Units 1, 2, and 3, this report 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: primary system pressure; containment building temperature; and containment pressure. As described within this report, sensor evaluations and data qualification required implementation of various processes, including comparisons with data from other sensors, analytical calculations, laboratory testing, and comparisons with sensors subjected to similar conditions in large-scale integral tests and with sensors that were similar in design to instruments easily removed from the TMI-2 plant for evaluations. As documented

  8. Literature review of environmental qualification of safety-related electric cables: Summary of past work. Volume 1

    SciTech Connect

    Subudhi, M.

    1996-04-01

    This report summarizes the findings from a review of published documents dealing with research on the environmental qualification of safety-related electric cables used in nuclear power plants. Simulations of accelerated aging and accident conditions are important considerations in qualifying the cables. Significant research in these two areas has been performed in the US and abroad. The results from studies in France, Germany, and Japan are described in this report. In recent years, the development of methods to monitor the condition of cables has received special attention. Tests involving chemical and physical examination of cable`s insulation and jacket materials, and electrical measurements of the insulation properties of cables are discussed. Although there have been significant advances in many areas, there is no single method which can provide the necessary information about the condition of a cable currently in service. However, it is possible that further research may identify a combination of several methods that can adequately characterize the cable`s condition.

  9. Benchmarking and qualification of the NUFREQ-NPW code for best estimate prediction of multi-channel core stability margins

    SciTech Connect

    Taleyarkhan, R.; Lahey, R.T. Jr.; McFarlane, A.F.; Podowski, M.Z.

    1988-01-01

    The NUFREQ-NPW code was modified and set up at Westinghouse, USA for mixed fuel type multi-channel core-wide stability analysis. The resulting code, NUFREQ-NPW, allows for variable axial power profiles between channel groups and can handle mixed fuel types. Various models incorporated into NUFREQ-NPW were systematically compared against the Westinghouse channel stability analysis code MAZDA-NF, for which the mathematical model was developed, in an entirely different manner. Excellent agreement was obtained which verified the thermal-hydraulic modeling and coding aspects. Detailed comparisons were also performed against nuclear-coupled reactor core stability data. All thirteen Peach Bottom-2 EOC-2/3 low flow stability tests were simulated. A key aspect for code qualification involved the development of a physically based empirical algorithm to correct for the effect of core inlet flow development on subcooled boiling. Various other modeling assumptions were tested and sensitivity studies performed. Good agreement was obtained between NUFREQ-NPW predictions and data. Moreover, predictions were generally on the conservative side. The results of detailed direct comparisons with experimental data using the NUFREQ-NPW code; have demonstrated that BWR core stability margins are conservatively predicted, and all data trends are captured with good accuracy. The methodology is thus suitable for BWR design and licensing purposes. 11 refs., 12 figs., 2 tabs.

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

    SciTech Connect

    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.

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

    SciTech Connect

    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.

  12. Simulations of neutralized final focus

    SciTech Connect

    Welch, D.R.; Rose, D.V.; Genoni, T.C.; Yu, S.S.; Barnard, J.J.

    2005-01-18

    In order to drive an inertial fusion target or study high energy density physics with heavy ion beams, the beam radius must be focused to < 3 mm and the pulse length must be compressed to < 10 ns. The conventional scheme for temporal pulse compression makes use of an increasing ion velocity to compress the beam as it drifts and beam space charge to stagnate the compression before final focus. Beam compression in a neutralizing plasma does not require stagnation of the compression, enabling a more robust method. The final pulse shape at the target can be programmed by an applied velocity tilt. In this paper, neutralized drift compression is investigated. The sensitivity of the compression and focusing to beam momentum spread, plasma, and magnetic field conditions is studied with realistic driver examples. Using the 3D particle-in-cell code, we examine issues associated with self-field generation, stability, and vacuum-neutralized transport transition and focusing.

  13. Final DOE Areas Feasibility Study

    Office of Legacy Management (LM)

    Management, Washington, DC Weiss Associates Environmental Science, Engineering and Management FINAL DOE AREAS FEASIBILITY STUDY for the: LABORATORY FOR ENERGY-RELATED HEALTH RESEARCH UNIVERSITY OF CALIFORNIA, DAVIS Prepared for: SM Stoller Corporation 2597 B ¾ Road Grand Junction, Colorado 81503 Prepared by: Weiss Associates 5801 Christie Avenue, Suite 600 Emeryville, California 94608-1827 March 07, 2008 Rev. 0 J:\DOE_STOLLER\4110\143\FEASIBILITY_STUDY\20080307_FS_TEXT_REV0.DOC WEISS ASSOCIATES

  14. 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

    Tandon, Lav; Colletti, Lisa M.; Drake, Lawrence R.; Lujan, Elmer J. W.; Garduno, Katherine

    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

  15. FORTE spacecraft vibration mitigation. Final report

    SciTech Connect

    Maly, J.R.

    1996-02-01

    This report documents work that was performed by CSA Engineering, Inc., for Los Alamos National Laboratory (LANL), to reduce vibrations of the FORTE spacecraft by retrofitting damped structural components into the spacecraft structure. The technical objective of the work was reduction of response at the location of payload components when the structure is subjected to the dynamic loading associated with launch and proto-qualification testing. FORTE is a small satellite that will be placed in orbit in 1996. The structure weighs approximately 425 lb, and is roughly 80 inches high and 40 inches in diameter. It was developed and built by LANL in conjunction with Sandia National Laboratories Albuquerque for the United States Department of Energy. The FORTE primary structure was fabricated primarily with graphite epoxy, using aluminum honeycomb core material for equipment decks and solar panel substrates. Equipment decks were bonded and bolted through aluminum mounting blocks to adjoining structure.

  16. Final Design RM | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Final Design RM Final Design RM The Final Design (FD) Review Module (RM) is a tool that assists Department of Energy (DOE) federal project review teams in evaluating the technical sufficiency of the final design prior to CD-3 approval. The FD RM focuses on the engineering design, technology, safety, and quality assurance to determine whether it meets overall design commitments, technical and safety requirements. Final Design RM (2.38 MB) More Documents & Publications Seismic Design

  17. Field practice internship final report

    SciTech Connect

    Foster, T.

    1994-05-01

    This field practice internship final report gives an overview of the field practice, which was completed at the Oak Ridge Y-12 Plant, Martin Marietta Energy Systems, Inc., Environmental Management Department, Oak Ridge, Tennessee. The field practice focused on the completion of the Superfund Amendments and Reauthorization Act (SARA) Title III, Emergency Planning and Community Right-to-Know Act Section 312, Tier II Report. The field practice internship was conducted on a full-time basis between December 13, 1993 through February 18, 1994. Sheila Poligone, Emergency Planning and Community Right-to-Know Act (EPCRA) Coordinator served as the field practice preceptor.

  18. Virtualized Network Control. Final Report

    SciTech Connect

    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.

  19. SPECIAL REREVIEW FINAL DETERMINATION UNCLASSIFIED

    Office of Legacy Management (LM)

    SPECIAL REREVIEW FINAL DETERMINATION UNCLASSIFIED , ?4~0180N SctuAnr P. 0. 00x *a STATION F New YORK, N. Y. IN RLPLY RCFSRTO EID?f A- 43 MS ~-7405 eng-8 ". Subject: Contract No.H-7405 eng-8 with Metal Hydrides Incorporated. MEMORAhDUM to the Files. 1. Reference is made to basi.c communication dated 27 September 1945, Symbol No. EIDM 1%-30-b, requesting certain information with respect to the subject contract. 2. Reference pars,?-raph a. The Government committed to restore Contractor's plant

  20. Hydroprocessing SRC. Final technical report

    SciTech Connect

    Bronfenbrenner, J.C.; Garg, D.; Harris, C.F.; Znaimer, S.

    1983-09-01

    Catalyst activity and aging rate were studied in ICRC's process development unit (PDU) and at the Wilsonville Advanced Coal Liquefaction Facility under SRC-I Demonstration Plant hydroprocessing conditions. Similar studies using both high- and low-conversion modes were conducted by The Lummus Company. The studies determined variations in SRC conversion, hydrocarbon gas production, hydrogen consumption, and heteroatom removal. Samples of spent catalyst were analyzed to ascertain the reasons for catalyst deactivation. Finally, the ICRC PDU hydroprocessing results were compared with those generated at Lummus and Wilsonville pilot plants.

  1. Hanford_FinalReport_20140130

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Energy Hanford workers begin cleaning out historic McCluskey Room Hanford workers begin cleaning out historic McCluskey Room Addthis Description Workers have entered one of the most hazardous rooms at the Hanford Site in Washington state to begin final cleanup of a room that became known to workers over the years by the name of a worker injured there in a Cold War-era accident. The first reentry on Monday, September 8, 2014, consisted mostly surveying the room. More information:

  2. [Experimental nuclear physics]. Final report

    SciTech Connect

    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.

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

    SciTech Connect

    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

  4. Final Information Quality Bulletin for Peer Review | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Final Information Quality Bulletin for Peer Review Final Information Quality Bulletin for Peer Review Final Information Quality Bulletin for Peer Review PDF icon Final Information ...

  5. Fort Polk EEAP. Final report

    SciTech Connect

    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.

  6. Strategic Asia 2002 Final Report

    SciTech Connect

    Richard Ellings; Aaron Friedberg; Michael Wills

    2002-09-01

    The Strategic Asia Program made considerable progress over the course of 2002--the program's first year with support from the Department of Energy--and completed all its tasks on schedule and within budget. Following a planning meeting in Washington in February 2002, a team of leading specialists wrote a series of original assessments regarding the impact of September 11 on the strategic environment in Asia, examining how perceptions and strategies of countries in the region changed following the terrorist attacks. The final products, Strategic Asia 2002-03: Asian Aftershocks and its accompanying executive summary, were published in September 2002. The program's research findings (some of which are summarized) were presented to policymakers in Washington and elsewhere throughout the year, and almost 2,000 copies of the book had been distributed by mid-2003.

  7. Microsoft Word - FINAL_TECHNICAL_REPORT.doc

    Office of Scientific and Technical Information (OSTI)

    ......... 27 Figure 16 Comparison between simulation and experimental results: (a) Top view of final simulated inclusion locations. ...

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

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

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

  9. GDB - Human Genome Database final report

    SciTech Connect

    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.

  10. CCSTF - Final Report | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    CCSTF - Final Report CCSTF - Final Report Carbon Capture and Storage Task Force - Final Report (2.08 MB) More Documents & Publications Before the Subcommittee on Energy -- House Science, Space, and Technology Committee Before the House Energy and Commerce Subcommittee on Oversight and Investigations CCS Task Force - Executive Summary

  11. Download the Final Agenda | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Final Agenda Download the Final Agenda SunShot Summit Agenda FINAL.pdf (1.11 MB) More Documents & Publications 2014 SunShot Summit Awardee Poster List Technology Forum Map and List of Awardees' Posters and Exhibits 2014 SunShot Initiative Concentrating Solar Power Subprogram Overview

  12. IRIS Final Technical Progress Report

    SciTech Connect

    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

  13. VERIFICATION OF THE DEFENSE WASTE PROCESSING FACILITY PROCESS DIGESTION METHOD FOR THE SLUDGE BATCH 6 QUALIFICATION SAMPLE

    SciTech Connect

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

    2010-06-09

    For each sludge batch that is processed in the Defense Waste Processing Facility (DWPF), the Savannah River National Laboratory (SRNL) confirms 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.1 DWPF SRAT samples are typically dissolved using a room temperature HF-HNO3 acid dissolution (i.e., DWPF Cold Chem (CC) Method, see DWPF Procedure SW4-15.201) and then analyzed by inductively coupled plasma - atomic emission spectroscopy (ICPAES). In addition to the CC method confirmation, the DWPF lab's mercury (Hg) digestion method was also evaluated for applicability to SB6 (see DWPF procedure 'Mercury System Operating Manual', Manual: SW4-15.204. Section 6.1, Revision 5, Effective date: 12-04-03). 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 digestion of Sludge Batch 6 (SB6) SRAT Receipt and SB6 SRAT Product samples. For validation of the DWPF lab's Hg method, only SRAT receipt material was used and compared to AR digestion results. The SB6 SRAT Receipt and SB6 SRAT Product samples were prepared in the SRNL Shielded Cells, and the SRAT Receipt material is representative of the sludge that constitutes the SB6 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 5 (SB5), to form the SB6 Blend composition. In addition to the 16 elements currently measured by the DWPF, this report includes Hg and thorium (Th) data (Th comprising {approx}2.5 - 3 Wt% of the total solids in SRAT Receipt and SRAT Product, respectively) and provides specific details of ICP-AES analysis of Th. Thorium was found to interfere with the U 367.007 nm emission line, and an inter-element correction (IEC) had to be applied to U data, which is also

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

    SciTech Connect

    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

  15. 2009 ECR FINAL REPORT 2010 | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    2009 ECR FINAL REPORT 2010 2009 ECR FINAL REPORT 2010 2009 ECR FINAL REPORT 2010 2009 ECR FINAL REPORT 2010 PDF icon 2009 ECR Report More Documents & Publications test Final ECR...

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

    SciTech Connect

    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.

  17. Final Report Package_Winnebago

    SciTech Connect

    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 Tribes 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 Tribes 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 Boards further development. A project summary book developed to include all key information, deliverables and utility provider data for the project. Winnebagos growth trends and expansion plans require the Tribe to play a more active role in assuring that

  18. Electric chiller handbook. Final report

    SciTech Connect

    1998-02-01

    that electric chillers are preferable to gas chillers in the large majority of applications, consistent with current market trends. Furthermore, today`s chillers offer a wide range of efficiencies and refrigerant options to serve cooling system needs for the 20-year lifetime of the chiller. Finally, new higher-efficiency models of electric chillers offer very attractive paybacks.

  19. Final report on SNAC 11

    SciTech Connect

    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

  20. Santa Barbara Final Technical Report

    SciTech Connect

    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

  1. Ameresco ESCO Qualification Sheet

    Energy Saver

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

  2. Qualification of Alternative Fuels

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    seal materials common; Fuels Considered Biodiesel o soy o palm o tallow o algae SVO - ... GTL- Gas-to-liquids Pyrolysis oil Biodiesel Blends - One Success Story Beginning in ...

  3. Notice of Final Rulemaking | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Final Rulemaking Notice of Final Rulemaking Revisions to U.S. Department of Energy (DOE) regulations governing compliance with the National Environmental Policy Act (NEPA) were published in the Federal Register on October 13, 2011, and will be effective on November 14. The revision (76 FR 63763) can be viewed using the link below. Final Rule - 76 FR 63763 - Oct 13 2011_0.pdf (297.74 KB) More Documents & Publications Department of Energy Technical Support Document National Environmental

  4. Hawaii Clean Energy Final PEIS Summary

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    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 Efficiency and Renewable Energy (DOE/EIS-0459) SEPTEMBER 2015 COVER SHEET TITLE: Hawai i Clean Energy Final Programmatic Environmental Impact Statement (Final PEIS) RESPONSIBLE FEDERAL AGENCY: U.S. Department of Energy (DOE), Offices of Electricity Delivery and Energy Reliability (OE) and Energy Efficiency and Renewable

  5. Technical Assessment Team Issues Final Report

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    , 2015 Technical Assessment Team Issues Final Report This week the Department of Energy's Technical Assessment Team (TAT) visited Carlsbad and met with federal and contractor staff ...

  6. Shortwave Hyperspectral Observations During MAGIC Final Campaign...

    Office of Scientific and Technical Information (OSTI)

    Title: Shortwave Hyperspectral Observations During MAGIC Final Campaign Summary The Marine ARM GPCI1 Investigation of Clouds (MAGIC) field campaign was initiated to improve our ...

  7. Final Rule Technical Amendment | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Final Rule Technical Amendment Federal Register Announcement: The Department of Energy (DOE) is publishing this technical amendment to the regulations for the loan guarantee ...

  8. EIS-0083: Final Environmental Impact Statement

    Office of Energy Efficiency and Renewable Energy (EERE)

    Final Northeast Regional Environmental Impact Statement; The Potential Conversion of Forty-Two Powerplants From Oil to Coal or Alternate Fuels

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

    OpenEI (Open Energy Information) [EERE & EIA]

    to: navigation, search OpenEI Reference LibraryAdd to library Report: Bureau of Land Management - Final Programmatic Environmental Impact Statement for Geothermal Leasing in the...

  10. Final Report - Hydrogen Delivery Infrastructure Options Analysis...

    Energy.gov [DOE] (indexed site)

    The project objective was to develop an understanding of hydrogen delivery options and plan related R&D efforts. Final Report - Hydrogen Delivery Infrastructure Options Analysis ...

  11. EIS-0251: Final Environmental Impact Statement

    Energy.gov [DOE]

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

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

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Customers subject to I-937 must acquire conservation independent of BPA's conservation acquisition efforts. In 2007, as BPA was finalizing its Regional Dialogue Policy, several...

  13. EA-1212-SA-01: Final Supplement Analysis

    Energy.gov [DOE]

    Final Supplement Analysis for the Environmental Assessment for the Lease of Land for the Development of a Research Park at Los Alamos National Laboratory

  14. Final Technical Report on Radioxenon Event Analysis

    SciTech Connect

    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.

  15. EA-1535: Final Programmatic Environmental Assessment | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    EA-1535: Final Programmatic Environmental Assessment Uranium Leasing Program Office of Legacy Management (LM) is evaluating its Uranium Leasing Program to determine a strategy for ...

  16. Final Report - Montana State University - Microbial Activity...

    Office of Scientific and Technical Information (OSTI)

    Media Citation Details In-Document Search Title: Final Report - Montana State University - Microbial Activity and Precipitation at Solution-Solution Mixing Zones in Porous Media ...

  17. Final Complex Transformation Supplemental Programmatic Environmental...

    Energy Saver

    National Nuclear Security Administration U.S. Department of Energy October 2008 C C CO O ... U.S. Department of Energy, National Nuclear Security Administration TITLE: Final ...

  18. Final Complex Transformation Supplemental Programmatic Environmental...

    Energy Saver

    Summary Summary DOEEIS-0236-S4 National Nuclear Security Administration U.S. Department ... U.S. Department of Energy, National Nuclear Security Administration TITLE: Final ...

  19. Final Complex Transformation Supplemental Programmatic Environmental...

    Energy Saver

    I Volume I Chapters 1 - 4 Chapters 1 - 4 DOEEIS-0236-S4 National Nuclear Security ... U.S. Department of Energy, National Nuclear Security Administration TITLE: Final ...

  20. Community Power Works Final Report and Conclusions

    SciTech Connect

    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.

  1. CONTRACTOR LEGAL MANAGEMENT REQUIREMENTS: APPLYING THE FINAL...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Attached is Acquisition Letter 2013-07, which provides suggested modification language. (The Final Rule's revisions are administrative in nature. Regarding costs contractors have ...

  2. Hawaii Clean Energy Final PEIS Summary

    Energy.gov [DOE] (indexed site)

    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 ...

  3. Clark Public Utilities Impact Evaluation Final Report

    U.S. Department of Energy (DOE) - all 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...

  4. Paducah Gaseous Diffusion Plant Final Environmental Assessment...

    Energy Saver

    Point of contact for more information: Robert Smith, Department of Energy-Paducah Paducah Gaseous Diffusion Plant Final Environmental Assessment for Potential Land and Facilities ...

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

    SciTech Connect

    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). Well 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

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

    SciTech Connect

    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

  7. EA-1941: Final Environmental Assessment | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Final Environmental Assessment EA-1941: Final Environmental Assessment BPA issued a Final EA to assess the potential environmental impacts of proposed improvements to 13 miles of ...

  8. EIS-0440: Final Environmental Impact Statement | Department of...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Final Environmental Impact Statement EIS-0440: Final Environmental Impact Statement Quartzsite Solar Energy Project The Final Environmental Impact Statement (FEIS) consists of a ...

  9. EIS-0312: Final Environmental Impact Statement | Department of...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Final Environmental Impact Statement EIS-0312: Final Environmental Impact Statement Fish and Wildlife Implementation Plan In this final environmental impact statement (FEIS), with...

  10. Portsmouth Site Treatment Plan Director's Final Findings and...

    Energy Saver

    Treatment Plan Director's Final Findings and Orders Portsmouth Site Treatment Plan Director's Final Findings and Orders Portsmouth Site Treatment Plan Director's Final Findings and ...

  11. EIS-0102: Final Environmental Impact Statement | Department of...

    Energy.gov [DOE] (indexed site)

    83 Wholesale Power Rate EIS-0102: Final Environmental Impact Statement More Documents & Publications EIS-0071: Final Environmental Impact Statement EIS-0202: Final Environmental...

  12. EA-1818: Final Environmental Assessment | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    8: Final Environmental Assessment EA-1818: Final Environmental Assessment Pettisville ... More Documents & Publications EA-1818: Finding of No Significant Impact EA-1820: Final ...

  13. EA-1008: Final Environmental Assessment | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    1008: Final Environmental Assessment EA-1008: Final Environmental Assessment Continued ... Environmental Assessment EA-1236: Finding of No Significant Impact EA-1956: Final

  14. EIS-0290: Final Environmental Impact Statement | Department of...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Final Environmental Impact Statement EIS-0290: Final Environmental Impact Statement Advanced Mixed Waste Treatment Project (AMWTP) The AMWTP Final EIS assesses the potential ...

  15. EIS-0407: Final Environmental Impact Statement | Department of...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Final Environmental Impact Statement EIS-0407: Final Environmental Impact Statement ... The Final Abengoa Biorefinery Project EIS evaluates the potential direct, indirect, and ...

  16. EIS-0336: Final Environmental Impact Statement | Department of...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Final Environmental Impact Statement EIS-0336: Final Environmental Impact Statement Tucson ... The Final EIS will be used by DOE and the Federal agency officials to ensure that they ...

  17. EIS-0271: Final Environmental Impact Statement | Department of...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Final Environmental Impact Statement EIS-0271: Final Environmental Impact Statement ... This EIS is linked to the Final Programmatic Environmental Impact Statement for Tritium ...

  18. EIS-0370: Final Environmental Impact Statement | Department of...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Final Environmental Impact Statement EIS-0370: Final Environmental Impact Statement Windy Gap Firming Project, Colorado Download Document EIS-0370: Final Environmental Impact Statement ...

  19. EIS-0089: Final Environmental Impact Statement | Department of...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    9: Final Environmental Impact Statement EIS-0089: Final Environmental Impact Statement ... The final environmental impact statement (EIS) consists of the draft EIS and the Addendum ...

  20. EIS-0447: Final Environmental Impact Statement | Department of...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Final Environmental Impact Statement EIS-0447: Final Environmental Impact Statement DOE prepared this Final EIS to evaluate the potential environmental impacts of a DOE proposal to ...