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1

AGC-3 Irradiation Data Qualification Final Report  

SciTech Connect (OSTI)

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.

Laurence Hull

2014-08-01T23:59:59.000Z

2

AGC-2 Irradiation Data Qualification Final Report  

SciTech Connect (OSTI)

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

Laurence C. Hull

2012-07-01T23:59:59.000Z

3

AGC-3 IRRADIATION DATA QUALIFICATION FINAL REPORT  

SciTech Connect (OSTI)

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

Hull, Laurence

2014-08-01T23:59:59.000Z

4

Experience gained from equipment qualification inspections  

SciTech Connect (OSTI)

This paper describes issues which have been identified during equipment qualification inspections. Generic qualification information is discussed first, such as qualification bases, utility/supplier interfaces, file auditability, and generic environmental qualification. Next, technical strategies with specific examples are discussed. Issues covered include functional performance requirements, post accident qualification, similarity, installation and interfaces, maintenance, aging, and testing. Finally, additions and deletions to equipment qualification master lists and environmental enveloping are discussed.

Jacobus, M.J.

1986-01-01T23:59:59.000Z

5

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

SciTech Connect (OSTI)

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

Pham, Binh T; Einerson, Jeffrey J

2014-07-01T23:59:59.000Z

6

Protective Force Firearms Qualification Courses  

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

Gun Qualification Course ... VII-4 CHAPTER VIII . LIGHT MACHINE GUN QUALIFICATION COURSES ..... VIII-1 1. Introduction ......

7

Assessor Training Assessor Qualification &  

E-Print Network [OSTI]

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

8

Final Assembly and Initial Irradiation of the First Advanced Gas Reactor Fuel Development and Qualification Experiment in the Advanced Test Reactor  

SciTech Connect (OSTI)

The United States Department of Energy’s Advanced Gas Reactor (AGR) Fuel Development and Qualification Program will be irradiating eight separate low enriched uranium (LEU) oxycarbide (UCO) tri-isotropic (TRISO) particle fuel (in compact form) experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). The ATR has a long history of irradiation testing in support of reactor development and the INL has been designated as the new United States Department of Energy’s lead laboratory for nuclear energy development. The ATR is one of the world’s premiere test reactors for performing long term, high flux, and/or large volume irradiation test programs. These irradiations and fuel development are being accomplished to support development of the next generation reactors in the United States. The AGR fuel experiments will be irradiated over the next ten years to demonstrate and qualify new particle fuel for use in high temperature gas reactors. The goals of the irradiation experiments are to provide irradiation performance data to support fuel process development, to qualify fuel for normal operating conditions, to support development and validation of fuel performance and fission product transport models and codes, and to provide irradiated fuel and materials for post irradiation examination (PIE) and safety testing.1,2 The experiments, which will each consist of six separate capsules, will be irradiated in an inert sweep gas atmosphere with individual on-line temperature monitoring and control of each capsule. The sweep gas will also have on-line fission product monitoring on its effluent to track performance of the fuel in each individual capsule during irradiation. The final design phase for the first experiment was completed in 2005, and the fabrication and assembly of the first experiment test train (designated AGR-1) as well as the support systems and fission product monitoring system that will monitor and control the experiment during irradiation were completed in 2006. The experiment was inserted in the ATR in December 2006, and will serve as a shakedown test of the multi-capsule experiment design that will be used in the subsequent irradiations as well as a test of the early variants of the fuel produced under this program. The experiment test train as well as the monitoring, control, and data collection systems are discussed.

S. B. Grover

2007-05-01T23:59:59.000Z

9

NORESCO ESCO Qualification Sheet  

Broader source: Energy.gov [DOE]

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).

10

Firearms Qualification Courses Manual  

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

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

2002-01-17T23:59:59.000Z

11

BEREA COLLEGE VENDOR QUALIFICATION FORM  

E-Print Network [OSTI]

BEREA COLLEGE VENDOR QUALIFICATION FORM 1. Name of Company submit the most recent financial statements with this vendor qualification form. 17. If you accept

Baltisberger, Jay H.

12

AGR-1 Data Qualification Report  

SciTech Connect (OSTI)

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 currently in review. 4. ATR Operating Conditions Data. Data for all AGR-1 cycles have been stored and capture tested. These data, which come from outside the VHTR program, are assumed to be qualified by ATR quality control procedures. 5. Neutronics and Thermal Modeling Data. NDMAS processing is in progress. These data will not be qualified by NDMAS.

Michael Abbott

2010-03-01T23:59:59.000Z

13

Firearms Qualification Courses Manual  

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

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.

1997-08-21T23:59:59.000Z

14

Business Case for Technical Qualification Program Accreditation...  

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

Business Case for Technical Qualification Program Accreditation Incentives Business Case for Technical Qualification Program Accreditation Incentives TQP Accreditation standardize...

15

Staubli TX-90XL robot qualification at the LLIHE.  

SciTech Connect (OSTI)

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.

Covert, Timothy Todd

2010-10-01T23:59:59.000Z

16

Qualification Status List (QSL Package)  

E-Print Network [OSTI]

qualification of Array B. These open items are summarized on page 2 and the equipment subsections which follow#12;ALSEP Qualification Status List (QSL Package) Flight 3 Configuration #12;NO. ltiY. NO. RI!V. NO. Qualification Status List ALSEP Array B Configuration 1. 0 INTRODUCTION ATM 825 PAGI! 1

Rathbun, Julie A.

17

Firearms Qualification Courses Manual  

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

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.

1997-07-08T23:59:59.000Z

18

AGR-1 Data Qualification Interim Report  

SciTech Connect (OSTI)

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.

Machael Abbott

2009-08-01T23:59:59.000Z

19

Firearms Qualification Courses Manual  

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

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.

1992-12-01T23:59:59.000Z

20

Schneider Electric ESCO Qualification Sheet  

Broader source: Energy.gov [DOE]

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).

Note: This page contains sample records for the topic "qualification final" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Lockheed Martin ESCO Qualification Sheet  

Broader source: 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).

22

ORISE: Training and Qualification Programs  

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

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

23

Johnson Controls ESCO Qualification Sheet  

Broader source: Energy.gov [DOE]

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).

24

Honeywell International ESCO Qualification Sheet  

Broader source: Energy.gov [DOE]

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).

25

RERTR Fuel Developmemt and Qualification Plan  

SciTech Connect (OSTI)

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

Dan Wachs

2007-01-01T23:59:59.000Z

26

FAQS Gap Analysis Qualification Card – Criticality Safety  

Broader source: Energy.gov [DOE]

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

27

FAQS Gap Analysis Qualification Card – Radiation Protection  

Broader source: Energy.gov [DOE]

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

28

FAQS Qualification Card - Civil Structural Engineering | Department...  

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

Civil Structural Engineering FAQS Qualification Card - Civil Structural Engineering A key element for the Department's Technical Qualification Programs is a set of common...

29

FAQS Gap Analysis Qualification Card – Environmental Restoration  

Broader source: Energy.gov [DOE]

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

30

FAQS Gap Analysis Qualification Card – Construction Management  

Broader source: Energy.gov [DOE]

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

31

FAQS Gap Analysis Qualification Card – Mechanical Systems  

Broader source: Energy.gov [DOE]

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

32

FAQS Qualification Card – Criticality Safety  

Broader source: Energy.gov [DOE]

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

33

FAQS Qualification Card- Aviation Manager  

Broader source: Energy.gov [DOE]

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

34

FAQS Qualification Card – Environment Compliance  

Broader source: Energy.gov [DOE]

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

35

FAQS Qualification Card – Environmental Restoration  

Broader source: Energy.gov [DOE]

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

36

FAQS Qualification Card – Waste Management  

Broader source: Energy.gov [DOE]

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

37

FAQS Qualification Card- Construction Management  

Broader source: Energy.gov [DOE]

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

38

FINAL  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicy andExsolutionFES Committees of VisitorsASCRReal-time2 FINAL

39

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

Office of Environmental Management (EM)

Gap Analysis Qualification Card - Senior Technical Safety Manager FAQS Gap Analysis Qualification Card - Senior Technical Safety Manager Functional Area Qualification Standard Gap...

40

Energy Systems Group ESCO Qualification Sheet | Department of...  

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

Energy Systems Group ESCO Qualification Sheet Energy Systems Group ESCO Qualification Sheet Document outlines the energy service company (ESCO) qualifications for Energy Systems...

Note: This page contains sample records for the topic "qualification final" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

Benham Companies ESCO Qualification Sheet  

Broader source: Energy.gov [DOE]

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).

42

Optimization Online - Constraint Qualification Failure in Second ...  

E-Print Network [OSTI]

Jul 22, 2014 ... ... Qualification Failure in Second-Order Cone Formulations of Unbounded Disjunctions" Technical Report - NICTA, Canberra ACT Australia, ...

Hassan L. Hijazi

2014-07-22T23:59:59.000Z

43

Committee on Educational Policy MAJOR QUALIFICATION POLICY  

E-Print Network [OSTI]

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

California at Santa Cruz, University of

44

Contract PQQ Pre-Qualification  

E-Print Network [OSTI]

Contract PQQ Pre-Qualification Questionnaire Design, Build and Installation of Interpretation within the new Welcome Building at Westonbirt, the National Arboretum Contract No: W156/F15.90 OJEU Ref: 2012-164242 #12;Contract PQQ 5a. Contract PQQ | 2 | Version 2 04/12 Introduction The Forestry

45

FPL Energy Services ESCO Qualification Sheet  

Broader source: 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).

46

Clark Energy Group ESCO Qualification Sheet  

Broader source: 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).

47

History of IEC Qualification Standards (Presentation)  

SciTech Connect (OSTI)

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

Wohlhgemuth, J.

2011-07-01T23:59:59.000Z

48

Pepco Energy Services ESCO Qualification Sheet  

Broader source: Energy.gov [DOE]

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).

49

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

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

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

50

Technical Qualification Program Self-Assessment Report - Savannah...  

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

Technical Qualification Program Self-Assessment Report - Savannah River Operations Office - 2010 Technical Qualification Program Self-Assessment Report - Savannah River Operations...

51

FAQS Gap Analysis Qualification Card – Fire Protection Engineering  

Broader source: Energy.gov [DOE]

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

52

FAQS Gap Analysis Qualification Card – Nuclear Explosive Safety Study  

Broader source: Energy.gov [DOE]

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

53

FAQS Qualification Card – Fire Protection Engineering  

Broader source: Energy.gov [DOE]

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

54

FAQS Qualification Card – Nuclear Explosive Safety Study  

Broader source: Energy.gov [DOE]

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

55

FAQS Qualification Card- Aviation Safety Officer  

Broader source: Energy.gov [DOE]

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

56

FAQS Qualification Card – Facility Maintenance Management  

Broader source: Energy.gov [DOE]

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

57

FAQS Qualification Card – Senior Technical Safety Manager  

Broader source: Energy.gov [DOE]

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

58

FAQS Qualification Card – Safeguards and Security  

Broader source: Energy.gov [DOE]

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

59

AGR-2 Data Qualification Report for ATR Cycle 154B  

SciTech Connect (OSTI)

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.

Binh Pham; Jeff Einerson

2014-01-01T23:59:59.000Z

60

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

E-Print Network [OSTI]

5. 2 5. 3 5.4 5.5 5. 6 5.7 Nodal Description Thermal Resistances Solar Heating Lunar SurfaceLSPE Qualification and Flight Acceptance T /V Test Su.m..mary and Thermal Design Final Report NO Thermal Control Systems. The report is divided into three sections. The first section introduces

Rathbun, Julie A.

Note: This page contains sample records for the topic "qualification final" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

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 (OSTI)

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.

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

2006-10-01T23:59:59.000Z

62

Siemens Government Services ESCO Qualification Sheet  

Broader source: Energy.gov [DOE]

Fact sheet outlines the energy service company (ESCO) qualification for Siemens Government Services in relation to the U.S. Department of Energy (DOE) energy savings performance contracts (ESPC).

63

New geothermal site identification and qualification. Final report  

SciTech Connect (OSTI)

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.

Not Available

2004-04-01T23:59:59.000Z

64

Changing nature of equipment and parts qualification  

SciTech Connect (OSTI)

Ideally, the original supplier of a piece of nuclear safety-related equipment has performed a qualification program and will continue to support that equipment throughout the lifetime of the nuclear power plants in which in equipment is installed. The supplier's nuclear quality assurance program will be maintained and he will continue to offer all necessary replacement parts. These parts will be identical to the original parts, certified to the original purchase order requirements, and the parts will be offered at competitive prices. Due to the changing nature of the nuclear plant equipment market, however, one or more of those ideal features are frequently unavailable when safety-related replacement equipment or parts are required. Thus, the process of equipment and parts qualification has had to adjust in order to ensure obtaining qualified replacements when needed. This paper presents some new directions taken in the qualification of replacement equipment and parts to meet changes in the marketplace.

Bucci, R.M.

1988-01-01T23:59:59.000Z

65

Achieving agility through parameter space qualification  

SciTech Connect (OSTI)

The A-primed (Agile Product Realization of Innovative electro-Mechanical Devices) project is defining and proving processes for agile product realization for the Department of Energy complex. Like other agile production efforts reported in the literature, A-primed uses concurrent engineering and information automation technologies to enhance information transfer. A unique aspect of our approach to agility is the qualification during development of a family of related product designs and their production processes, rather than a single design and its attendant processes. Applying engineering principles and statistical design of experiments, economies of test and analytic effort are realized for the qualification of the device family as a whole. Thus the need is minimized for test and analysis to qualify future devices from this family, thereby further reducing the design-to-production cycle time. As a measure of the success of the A-primed approach, the first design took 24 days to produce, and operated correctly on the first attempt. A flow diagram for the qualification process is presented. Guidelines are given for implementation, based on the authors experiences as members of the A-primed qualification team.

Diegert, K.V.; Easterling, R.G.; Ashby, M.R.; Benavides, G.L.; Forsythe, C.; Jones, R.E.; Longcope, D.B.; Parratt, S.W.

1995-02-01T23:59:59.000Z

66

Request for Qualifications for Sacramento Landfill  

Broader source: 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.

67

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

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

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

68

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

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

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

69

Safety critical software development qualification  

SciTech Connect (OSTI)

With the increasing use of digital systems in control applications, customers must acquire appropriate expectations for software development and quality assurance procedures. Purchasers and users of digital systems need to understand the benefits to the supplier of effective quality systems. These systems consist not only of procedures but tools that enable automation. Without the use of automation, quality can not be assured. A software and systems quality program starts with the documents you are very familiar with. But these documents must define more than the final system. They must address specific development environment characteristics and testing capabilities. Starting with the RFP, some of the items that should be introduced are Software Configuration Management, regression testing and defect tracking. The digital system customer is in the best position to enforce the use of software and systems quality programs by including them in project requirements as early as the Purchase Order. The customer's understanding of the full scope and implementation of a software quality program is essential to achieving the quality necessary in nuclear projects, and, incidentally, completing those projects on schedule. (authors)

Marron, J. E. [Invensys Process Systems, 33 Commercial Street, Foxboro, MA 02035 (United States)

2006-07-01T23:59:59.000Z

70

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

Broader source: Energy.gov [DOE]

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

71

Department for Education Assessment, Curriculum and General Qualifications  

E-Print Network [OSTI]

Department for Education Assessment, Curriculum and General Qualifications Reform Group Level 6 and General Qualifications Reform Group 2 St Paul's Place 125 Norfolk Street Sheffield, S1 2FJ Dear Mrs Ward National Curriculum Reform (England): Key Stage 4 Science I am writing in response to your current

Rambaut, Andrew

72

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

SciTech Connect (OSTI)

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.

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

2014-03-01T23:59:59.000Z

73

Qualification Testing Evaluation (QTE) program for safety-related equipment  

SciTech Connect (OSTI)

The nuclear power industry is required to demonstrate that certain safety-related equipment is ''qualified'' and will function even in the event of a severe reactor accident. Demonstration of qualification by testing is the preferred approach. International interest in equipment qualification, and its recognition as being paramount to safety, is rapidly increasing, with most major supplier-countries developing sophisticated qualification testing facilities. An aspect of the demonstration of qualification is to assure that the qualification testing applied to safety-related equipment is both realistic and conservative; that is, a program of qualification methodology assessment and improvement is imperative. In the United States, the Nuclear Regulatory Commission (NRC) is sponsoring the Qualification Testing Evaluation Program with the goal of obtaining data that will confirm or improve the technical bases for equipment qualification programs. This multi-task Program has long-term, continuing objectives, but recent new results have been obtained and these results are being incorporated into NRC regulations with attendant impact on the nuclear industry. 19 refs. (JDB)

Bonzon, L.L.; Gillen, K.T.; Clough, R.L.; Salazar, E.A.; Buckalew, W.H.; Thome, F.V.; Stuetzer, O.M.; Feit, R.

1980-01-01T23:59:59.000Z

74

FAQS Qualification Card – Safeguards and Security General Technical Base  

Broader source: Energy.gov [DOE]

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

75

Large Bore Powder Gun Qualification (U)  

SciTech Connect (OSTI)

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.

Rabern, Donald A. [Los Alamos National Laboratory; Valdiviez, Robert [Los Alamos National Laboratory

2012-04-02T23:59:59.000Z

76

High-level waste qualification: Managing uncertainty  

SciTech Connect (OSTI)

Qualification of high-level waste implies specifications driven by risk against which performance can be assessed. The inherent uncertainties should be addressed in the specifications and statistical methods should be employed to appropriately manage these uncertainties. Uncertainties exist whenever measurements are obtained, sampling is employed, or processes are affected by systematic or random perturbations. This paper presents the approach and statistical methods currently employed by Pacific Northwest Laboratory (PNL) and West Valley Nuclear Services (WVNS) to characterize, minimize, and control uncertainties pertinent to a waste-form acceptance specification concerned with product consistency.

Pulsipher, B.A. [Pacific Northwest Lab., Richland, WA (United States)

1993-12-31T23:59:59.000Z

77

Qualifications | Y-12 National Security Complex  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 - SeptemberMicroneedlesAdvancedJanuary 13,PuttingEnergy QER1 Qualifications

78

Heat Treatment Procedure Qualification for Steel Castings  

SciTech Connect (OSTI)

The science of heat treatment has been well studied and is the basis from which existing specifications and practices for the heat treatment of steel castings have been developed. Although these existing specifications address the general needs of steel castings to be heat-treated, they do not take into account the variability in the parameters that govern the processes. The need for a heat treatment qualification procedure that accounts for this variability during heat treatment is an important step toward heat treatment quality assurance. The variability in temperatures within a heat treatment furnace is one such variable that a foundry has to contend with in its day-to-day activity. Though specifications indicate the temperatures at which a particular heat treatment has to be conducted, heat treatment specifications do not adequately account for all aspects of heat treatment quality assurance. The heat treatment qualification procedure will comprise of a robust set of rules and guidelines that ensure that foundries will still be able to operate within the set of constraints imposed on them by non-deterministic elements within the processes.

Professor Robert C. Voigt

2003-02-02T23:59:59.000Z

79

Equipment qualification issues research and resolution: Status report  

SciTech Connect (OSTI)

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.

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

1986-11-01T23:59:59.000Z

80

ITER CENTRAL SOLENOID COIL INSULATION QUALIFICATION  

SciTech Connect (OSTI)

An insulation system for ITER Central Solenoid must have sufficiently high electrical and structural strength. Design efforts to bring stresses in the turn and layer insulation within allowables failed. It turned out to be impossible to eliminate high local tensile stresses in the winding pack. When high local stresses can not be designed out, the qualification procedure requires verification of the acceptable structural and electrical strength by testing. We built two 4 x 4 arrays of the conductor jacket with two options of the CS insulation and subjected the arrays to 1.2 million compressive cycles at 60 MPa and at 76 K. Such conditions simulated stresses in the CS insulation. We performed voltage withstand tests and after end of cycling we measured the breakdown voltages between in the arrays. After that we dissectioned the arrays and studied micro cracks in the insulation. We report details of the specimens preparation, test procedures and test results.

Martovetsky, N N; Mann, T L; Miller, J R; Freudenberg, K D; Reed, R P; Walsh, R P; McColskey, J D; Evans, D

2009-06-11T23:59:59.000Z

Note: This page contains sample records for the topic "qualification final" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

ITER Central Solenoid Coil Insulation Qualification  

SciTech Connect (OSTI)

An insulation system for ITER Central Solenoid must have sufficiently high electrical and structural strength. Design efforts to bring stresses in the turn and layer insulation within allowables failed. It turned out to be impossible to eliminate high local tensile stresses in the winding pack. When high local stresses can not be designed out, the qualification procedure requires verification of the acceptable structural and electrical strength by testing. We built two 4x4 arrays of the conductor jacket with two options of the CS insulation and subjected the arrays to 1.2 million compressive cycles at 60 MPa and at 76 K. Such conditions simulated stresses in the CS insulation. We performed voltage withstand tests and after end of cycling we measured the breakdown voltages between in the arrays. After that we dissectioned the arrays and studied micro cracks in the insulation. We report details of the specimens preparation, test procedures and test results.

Martovetsky, Nicolai N [ORNL] [ORNL; Mann Jr, Thomas Latta [ORNL] [ORNL; Miller, John L [ORNL] [ORNL; Freudenberg, Kevin D [ORNL] [ORNL; Reed, Richard P [Cryogenic Materials, Inc.] [Cryogenic Materials, Inc.; Walsh, Robert P [Florida State University] [Florida State University; McColskey, J D [National Institute of Standards and Technology (NIST), Boulder] [National Institute of Standards and Technology (NIST), Boulder; Evans, D [Advanced Cryogenic Materials] [Advanced Cryogenic Materials

2010-01-01T23:59:59.000Z

82

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

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

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

83

SRNL PHASE 1 ASSESSMENT OF THE WTP WASTE QUALIFICATION PROGRAM  

SciTech Connect (OSTI)

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

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

2012-03-06T23:59:59.000Z

84

Secondary Waste Cast Stone Waste Form Qualification Testing Plan  

SciTech Connect (OSTI)

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

Westsik, Joseph H.; Serne, R. Jeffrey

2012-09-26T23:59:59.000Z

85

Workshop on environmental qualification of electric equipment  

SciTech Connect (OSTI)

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.

Lofaro, R.; Gunther, W.; Villaran, M.; Lee, B.S.; Taylor, J. [comps.] [Brookhaven National Lab., Upton, NY (United States)

1994-05-01T23:59:59.000Z

86

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

SciTech Connect (OSTI)

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

Muller, M.

2012-03-01T23:59:59.000Z

87

SLUDGE BATCH 7B QUALIFICATION ACTIVITIES WITH SRS TANK FARM SLUDGE  

SciTech Connect (OSTI)

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

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

2011-11-16T23:59:59.000Z

88

Issues in the flight qualification of a space power reactor  

SciTech Connect (OSTI)

This paper presents an overview of the Nuclear Electric Propulsion Space Test Program (NEPSTP). The program goals, the proposed mission, the spacecraft, and the Topaz II space nuclear power system are described. The subject of flight qualification is examined and the inherent difficulties of qualifying a space reactor are described. The differences between US and Russian flight qualification procedures are explored. A plan is then described that was developed to determine an appropriate flight qualification program for the Topaz II reactor to support a possible NEPSTP launch. Refocusing of the activities of the Ballistic Missile Defense Organization (BMDO), combined with budgetary pressures, forced the cancellation of the NEPSTP at the end of the 1993 fiscal year.

Polansky, G.F. [Phillips Lab., Albuquerque, NM (United States); Schmidt, G.L. [New Mexico Engineering Research Inst., Albuquerque, NM (United States); Voss, S.S. [Los Alamos National Lab., NM (United States); Reynolds, E.L. [Applied Physics Lab., Laurel, MD (United States)

1994-10-01T23:59:59.000Z

89

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

SciTech Connect (OSTI)

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.

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

2013-04-26T23:59:59.000Z

90

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

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

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

2001-07-12T23:59:59.000Z

91

Decant pump assembly and controls qualification testing - test report  

SciTech Connect (OSTI)

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.

Staehr, T.W., Westinghouse Hanford

1996-05-02T23:59:59.000Z

92

Code qualification of structural materials for AFCI advanced recycling reactors.  

SciTech Connect (OSTI)

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

Natesan, K.; Li, M.; Majumdar, S.; Nanstad, R.K.; Sham, T.-L. (Nuclear Engineering Division); (ORNL)

2012-05-31T23:59:59.000Z

93

Environmental Compliance Functional Area Qualification Standard  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Career Scientists'Montana.Program -DepartmentNovember 1, 2010 EA-1797: Final EnvironmentalApril

94

Training and Qualification Program at the Saturn Facility  

SciTech Connect (OSTI)

This report describes the Training and Qualification Program at the Saturn Facility. The main energy source at Saturn is the Saturn accelerator which is used to test military hardware for vulnerability to X-rays, as well as to perform various types of plasma radiation source experiments. The facility is operated and maintained by a staff of twenty scientists and technicians. This program is designed to ensure these personnel are adequately trained and qualified to perform their jobs in a safe and efficient manner. Copies of actual documents used in the program are included as appendices. This program meets all the requirements for training and qualification in the DOE Orders on Conduct of Operations and Quality Assurance, and may be useful to other organizations desiring to come into compliance with these orders.

Artman, W.D.; Sullivan, J.J.; De La O, R.V.; Zawadzkas, G.A.

1993-01-01T23:59:59.000Z

95

Training and Qualification Program at the Simulation Technology Laboratory  

SciTech Connect (OSTI)

This report describes the Training and Qualification Program at the Simulation Technology Laboratory (STL). The main facility at STL is Hermes III, a twenty megavolt accelerator which is used to test military hardware for vulnerability to gamma-rays. The facility is operated and maintained by a staff of twenty engineers and technicians. This program is designed to ensure that these personnel are adequately trained and qualified to perform their jobs in a safe and efficient manner. Copies of actual documents used in the program are included in appendices. This program meets all the requirements for training and qualification in the DOE Orders on Conduct of Operations and Quality Assurance, and may be useful to other organizations desiring to come into compliance with these orders.

Zawadzkas, G.A.

1992-03-01T23:59:59.000Z

96

High Temperature Materials Interim Data Qualification Report FY 2011  

SciTech Connect (OSTI)

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.

Nancy Lybeck

2011-08-01T23:59:59.000Z

97

Plutonium metal and oxide container weld development and qualification  

SciTech Connect (OSTI)

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.``

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

1996-01-01T23:59:59.000Z

98

Qualification of NDE personnel in the nuclear industry  

SciTech Connect (OSTI)

There has been evidence of ineffective programs for certifying nondestructive examination (NDE) personnel who conduct periodic inservice examinations in nuclear power plants under ASME Section XI Code requirements. This was brought to the attention of a group from the electric utility industry, the Electric Power Research Institute (EPRI), some NDE consultants and representatives from the American Society of Mechanical Engineers (ASME) by the Nuclear Regulatory Commission (NRC) in a May, 1982 meeting in Bethesda, Maryland. One problem pointed out by the NRC was the lack of a clear definition of qualification requirements for certification of NDE personnel who conduct ASME Section XI Inservice Inspection work in nuclear power plants. The NRC requested that the nuclear industry resolve this problem by formulating definitive qualification requirements for personnel certification that could be made an industry requirement. In June, 1982 the EPRI NDE Subcommittee held a general meeting for utility representatives to discuss the results of the May, 1982 meeting to develop a plan for industry response to the issue. The consensus was that an Ad Hoc Committee of utility representatives be convened to develop a document outlining qualification requirements for vertification of NDE personnel. The Ad Hoc Committee was formally convened on September 29, 1982.

Epps, T.N.

1984-06-01T23:59:59.000Z

99

Additions to list of Nominating Bodies Organisation Website and Address Qualifications for nominating  

E-Print Network [OSTI]

Annex A Additions to list of Nominating Bodies Organisation Website and Address Qualifications plc is the world's leading semiconductor intellectual property supplier. Instead of bearing the costs

Glasgow, University of

100

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

Broader source: Energy.gov [DOE]

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

Note: This page contains sample records for the topic "qualification final" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

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

Broader source: Energy.gov [DOE]

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

102

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

SciTech Connect (OSTI)

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.

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

2005-09-30T23:59:59.000Z

103

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

SciTech Connect (OSTI)

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

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

2005-09-30T23:59:59.000Z

104

Qualification tests of materials for spallation neutron sources  

SciTech Connect (OSTI)

Several existing and planned facilities, worldwide, use protons at 650-2000 MeV to produce neutrons by spallation reactions. In the advanced spallation neutron sources, materials in the target and blanket structures will be exposed to high-energy proton fluences at 10{sup 25}-10{sup 26}/m{sup 2} per year. Information obtained in fusion reactor studies are being applied to the design of spallation neutron sources. The APT project is sponsoring a materials qualification program including irradiations in the proton beam and neutron field at the Los Alamos Spallation Radiation Damage Facility.

Sommer, W.F.

1996-12-31T23:59:59.000Z

105

FAQS Qualification Card - Mechanical Systems | Department of Energy  

Energy Savers [EERE]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of Inspector General Office of Audit|Department of Energy56Executive212-2012FAQS Job TaskFAQS Qualification

106

Seismic equipment qualification at Rocky Flats Plant: Lessons learned  

SciTech Connect (OSTI)

Seismic equipment qualification is being evaluated as a part of the Systematic Evaluation Program (SEP) at Rocky Flats Plant (RFP). Initially it was believed that the experience database developed by the Seismic Qualification Utility Group (SQUG) for commercial nuclear power plants, as outlined in their Generic Implementation Procedure (GIP), would provide a substantial benefit for the seismic adequacy verification of equipment at RFP. However, further review of the simplified guidelines contained in the GIP with respect to the specific RFP structures and components revealed substantial differences from the GIP criteria. Therefore, the number of ``outliers`` from the experience database defined in the GIP is greater than was initially anticipated. This paper presents details of the differences found between the RFP structures and components and those represented in the GIP, and the challenges presented for their evaluation at RFP. Approaches necessary to develop seismic verification data are also discussed. The discussions focus on experience with one of the nuclear facilities at RFP, Building 707. However, the conclusions are generally applicable to other similar facilities that typically comprise the RFP nuclear facilities.

Peregoy, W.; Herring, K.

1993-08-01T23:59:59.000Z

107

Qualification tests for {sup 192}Ir sealed sources  

SciTech Connect (OSTI)

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.

Iancso, Georgeta, E-mail: georgetaiancso@yahoo.com; Iliescu, Elena, E-mail: georgetaiancso@yahoo.com; Iancu, Rodica, E-mail: georgetaiancso@yahoo.com [National Institute of R and D for Physics and Nuclear Engineering Horia Hulubei, Magurele (Romania)

2013-12-16T23:59:59.000Z

108

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

SciTech Connect (OSTI)

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.

Tamizhmani, Govindasamy (Arizona State University, Tempe, AZ); Granata, Jennifer E.; Maracas, George (Arizona State University, Tempe, AZ); Ayyanar, Raja (Arizona State University, Tempe, AZ); Marinella, Matthew; Venkataramanan, Sai Balasubramanian Alampoondi (Arizona State University, Tempe, AZ)

2011-06-01T23:59:59.000Z

109

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

SciTech Connect (OSTI)

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)

Markillie, Jeffrey R.; Arakali, Aruna V.; Benson, Peter A.; Halverson, Thomas G. [Hanford Tank Waste Treatment and Immobilization Plant Project, Richland, WA 99354 (United States)] [Hanford Tank Waste Treatment and Immobilization Plant Project, Richland, WA 99354 (United States); Adamson, Duane J.; Herman, Connie C.; Peeler, David K. [Savannah River National Laboratory, Aiken, SC 29808 (United States)] [Savannah River National Laboratory, Aiken, SC 29808 (United States)

2013-07-01T23:59:59.000Z

110

Final Report  

SciTech Connect (OSTI)

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.

Biros, George

2014-08-18T23:59:59.000Z

111

Final Report  

SciTech Connect (OSTI)

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.

DeTar, Carleton [P.I.

2012-12-10T23:59:59.000Z

112

Experience with the implementation of a risk-based ISI program and inspection qualification  

SciTech Connect (OSTI)

Rolls Royce and Associates (RRA) are the Design Authority (DA) for Nuclear Steam Raising Plant (NSRP) used for the Royal Naval Nuclear Fleet. Over the past seven years RRA, with support from the Ministry of Defense, has developed and implemented a risk based in-service inspection (RBISI) strategy for the NSRP. Having used risk as a means of optimizing where to inspect, an inspection qualification (IQ) process has now been put in place to ensure that proposed inspections deliver the expected gains assumed. This qualification process follows very closely that currently being put forward by the European Network on Inspection Qualification (ENIQ).

Chapman, O.J.V. [Rolls Royce and Associates Ltd., Derby (United Kingdom)

1996-12-01T23:59:59.000Z

113

EDS V25 containment vessel explosive qualification test report.  

SciTech Connect (OSTI)

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.

Rudolphi, John Joseph

2012-04-01T23:59:59.000Z

114

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

SciTech Connect (OSTI)

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.

Binh T. Pham

2014-02-01T23:59:59.000Z

115

Final Proposal  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicyFeasibilityField Office ProgramsFinal7, 2014NovemberFinal-Proposal

116

Final Reminder:  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicyFeasibilityField Office ProgramsFinal7,Administrator's RecordFinal

117

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

Broader source: 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.

118

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

Broader source: Energy.gov [DOE]

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

119

IEEE Standard for qualification of Class 1E lead storage batteries for nuclear power generating stations  

SciTech Connect (OSTI)

This document describes qualification methods for Class 1E lead storage batteries and racks to be used in nuclear power generating stations outside of primary containment. Qualification required in ANSI/IEEE Std 279-1979 and IEEE Std 308-1978, can be demonstrated by using the procedures provided in this Standard in accordance with IEEE Std 323-1974. Battery sizing, maintenance, capacity testing, installation, charging equipment and consideration of other types batteries are beyond the scope of this Standard.

Not Available

1980-01-01T23:59:59.000Z

120

Enhanced personnel qualification requirements for ASME (American Society for Mechanical Engineers) Code Section 11 examinations  

SciTech Connect (OSTI)

One of the most important parts of a nondestructive examination (NDE) system, which consists of the equipment, procedure, and personnel for performing examinations, is the personnel who operate the equipment and analyze the examination results. Recent activity in Section 11 of the American Society for Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Committee to develop rules for personnel qualification for ultrasonic examinations is reviewed, and the proposed rules are compared with present day NDE personnel qualification practices.

Cook, J.F.

1987-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "qualification final" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

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

Broader source: Energy.gov [DOE]

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

122

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

SciTech Connect (OSTI)

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.

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

1993-05-01T23:59:59.000Z

123

Fuel qualification plan for the Advanced Neutron Source Reactor  

SciTech Connect (OSTI)

This report describes the development and qualification plan for the fuel for the Advanced Neutron Source. The reference fuel is U{sub 3}Si{sub 2}, dispersed in aluminum and clad in 6061 aluminum. This report was prepared in May 1994, at which time the reference design was for a two-element core containing highly enriched uranium (93% {sup 235}U) . The reactor was in the process of being redesigned to accommodate lowered uranium enrichment and became a three-element core containing a higher volume fraction of uranium enriched to 50% {sup 235}U. Consequently, this report was not issued at that time and would have been revised to reflect the possibly different requirements of the lower-enrichment, higher-volume fraction fuel. Because the reactor is now being canceled, this unrevised report is being issued for archival purposes. The report describes the fabrication and inspection development plan, the irradiation tests and performance modeling to qualify performance, the transient testing that is part of the safety program, and the interactions and interfaces of the fuel development with other tasks.

Copeland, G.L.

1995-07-01T23:59:59.000Z

124

Technology transfer equipment qualification methodology for shelf life determination  

SciTech Connect (OSTI)

Discussions with a number of Nuclear Utilities revealed that equipment qualified for 10 to 40 years in the harsh environment of the plant was being assigned shelf lives of only 5 to 10 years in the benign environment of the warehouse, and then the materials were being trashed. One safety-related equipment supplier was assigning a 10-year qualified life, from date of shipment, with no recognition of the difference in the aging rate in the plant vs. that in the warehouse. Many suppliers assign shelf lives based on product warranty considerations rather than actual product degradation. An EPRI program was initiated to evaluate the methods used to assign shelf lives and to adapt the Arrhenius methodology, used in equipment qualification, to assign technically justifiable shelf lives. Temperature is the main factor controlling shelf life; however, atmospheric pressure, humidity, ultraviolet light, ozone and other atmospheric contaminants were also considered. A list of 70 representative materials was addressed in the program. All of these were found to have shelf lives of 14 years to greater than 60 years, except for 19 items. For 18 of these items, there was no data available except for the manufacturer`s recommendation.

Anderson, J.W. [Wyle Labs., Huntsville, AL (United States)] [Wyle Labs., Huntsville, AL (United States)

1995-08-01T23:59:59.000Z

125

Final Report  

SciTech Connect (OSTI)

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.

R Paul Drake

2004-01-12T23:59:59.000Z

126

FINAL REPORT  

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

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127

Final Proposal  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicyFeasibilityField Office ProgramsFinal7,

128

Final-3  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicyFeasibilityField Office Final Tank Closure and Wastedecisions

129

Final Optics  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-Series toESnet4:EpitaxialtransatlanticUnified ForcesFile Systems FileVault1Final

130

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

SciTech Connect (OSTI)

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

Peters, T. B.

2013-02-26T23:59:59.000Z

131

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

SciTech Connect (OSTI)

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.

NONE

1996-03-01T23:59:59.000Z

132

Technical basis for environmental qualification of microprocessor-based safety-related equipment in nuclear power plants  

SciTech Connect (OSTI)

This document presents the results of studies sponsored by the Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. The studies were conducted by Oak Ridge National Laboratory (ORNL), Sandia National Laboratories (SNL), and Brookhaven National Laboratory (BNL). The studies address the following: (1) adequacy of the present test methods for qualification of digital I and C systems; (2) preferred (i.e., Regulatory Guide-endorsed) standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging for equipment to be located in a benign environment; and (5) determination of an appropriate approach for addressing the impact of smoke in digital equipment qualification programs. Significant findings from the studies form the technical basis for a recommended approach to the environmental qualification of microprocessor-based safety-related equipment in nuclear power plants.

Korsah, K.; Wood, R.T. [Oak Ridge National Lab., TN (United States); Hassan, M. [Brookhaven National Lab., Upton, NY (United States); Tanaka, T.J. [Sandia National Labs., Albuquerque, NM (United States)

1998-01-01T23:59:59.000Z

133

Final Report  

SciTech Connect (OSTI)

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).

Webb, Robert C. [Texas A& M University] [Texas A& M University; Kamon, Teruki [Texas A& M University] [Texas A& M University; Toback, David [Texas A& M University] [Texas A& M University; Safonov, Alexei [Texas A& M University] [Texas A& M University; Dutta, Bhaskar [Texas A& M University] [Texas A& M University; Dimitri, Nanopoulos [Texas A& M University] [Texas A& M University; Pope, Christopher [Texas A& M University] [Texas A& M University; White, James [Texas A& M University] [Texas A& M University

2013-11-18T23:59:59.000Z

134

Non-destructive qualification tests for ITER cryogenic axial insulating breaks  

SciTech Connect (OSTI)

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.

Kosek, Jacek [Wroclaw University of Technology, Wybrzeze Wyspianskiego 27, 50-370 Wroclaw, Poland and CERN, Geneva 23,CH-1211 (Switzerland); Lopez, Roberto; Tommasini, Davide [CERN, Geneva 23,CH-1211 (Switzerland); Rodriguez-Mateos, Felix [CERN, Geneva 23,CH-1211, Switzerland and ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul lez Durance (France)

2014-01-29T23:59:59.000Z

135

OREGON STATE UNIVERSITY (OSU) TRAINING RESEARCH ISOTOPE GENERAL ATOMICS (TRIGA) OVERPACK CLOSURE WELDING PROCESS PARAMETER DEVELOPMENT & QUALIFICATION  

SciTech Connect (OSTI)

Spent Nuclear Fuel (SNF) from the Oregon State University (OSU) TRIGA{reg_sign} Reactor is currently being stored in thirteen 55-gallon drums at the Hanford Site's low-level burial grounds. This fuel is soon to be retrieved from buried storage and packaged into new containers (overpacks) for interim storage at the Hanford Interim Storage Area (ISA). One of the key activities associated with this effort is final closure of the overpack by welding. The OSU fuel is placed into an overpack, a head inserted into the overpack top, and welded closed. Weld quality, for typical welded fabrication, is established through post-weld testing and nondestructive examination (NDE); however, in this case, once the SNF is placed into the overpack, routine testing and NDE are not feasible. An alternate approach is to develop and qualify the welding process/parameters, demonstrate beforehand that they produce the desired weld quality, and then verify parameter compliance during production welding. Fluor engineers have developed a Gas Tungsten Arc Welding (GTAW) technique and parameters, demonstrating that weld quality requirements for closure of packaged SNF overpacks are met, using this alternate approach. The following reviews the activities performed for this development and qualification effort.

CANNELL, G.R.

2006-09-11T23:59:59.000Z

136

Model Request for Qualifications to Pre-Qualify Energy Service Companies  

Broader source: Energy.gov [DOE]

This page contains model Request for Qualifications (RFQ) 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 the state.

137

Request for Qualifications for Developers for the Lawrence Berkeley National Lab (LBNL)  

E-Print Network [OSTI]

Request for Qualifications for Developers for the Lawrence Berkeley National Lab (LBNL) Second for the Lawrence Berkeley National Lab (LBNL) Second Campus at the Richmond Field Station I. Introduction for the Lawrence Berkeley National Lab (LBNL) Second Campus. The Second Campus will be home to a state

Walker, Matthew P.

138

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

Broader source: Energy.gov [DOE]

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

139

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

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

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.

2010-04-21T23:59:59.000Z

140

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

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

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, cancels DOE O 426.2.

2010-04-21T23:59:59.000Z

Note: This page contains sample records for the topic "qualification final" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

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

SciTech Connect (OSTI)

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.

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

2012-12-20T23:59:59.000Z

142

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

SciTech Connect (OSTI)

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.

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

2012-12-11T23:59:59.000Z

143

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

Broader source: Energy.gov [DOE]

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

144

Nondestructive Evaluation Quality Procedure: Personnel Qualification and Certification Radiographic Testing-Levels I& II  

SciTech Connect (OSTI)

This Operational Procedure establishes the minimum requirements for the qualification and certification/recertification of Nondestructive Evaluation (NDE) personnel in the nondestructive testing (NDT) radiographic testing (RT) method. This document is in accordance with the American Society for Nondestructive Testing Recommended Practice SNT-TC-1A, 1996, except as amended herein.

Dolan, K; Rikard, R D; Rodriquez, J

2003-07-01T23:59:59.000Z

145

Independent qualification testing is a prerequisite in over 40 U.S. states for seeking  

E-Print Network [OSTI]

Independent qualification testing is a prerequisite in over 40 U.S. states for seeking, and now primarily involve pre- Standard equipment, untested equipment configura- tions, or the mismanagement of tested equipment. Overall, systems integrity and the election processes have improved markedly

Rivest, Ronald L.

146

DATA QUALIFICATION REPORT: MAJOR ION AND PH DATA FOR USE ON THE YUCCA MOUNTAIN PROJECT  

SciTech Connect (OSTI)

This data qualification report uses technical assessment and corroborating data methods according to Attachment 2 of AP-SIII.2Q, Rev. 0, ICN 2, ''Qualification of Unqualified Data and the Documentation of Rationale for Accepted Data'', to qualify major ion and pH data. This report was prepared in accordance with Data Qualification Plan TDP-NBS-GS-00003 1, Revision 2. Additional reports will be prepared to address isotopic and precipitation-related data. Most of the data considered in this report were acquired and developed by the U.S. Geological Survey (USGS). The data qualification team considers the sampling and analytical protocols employed by the USGS over the time period of data acquisition to be state-of-the-art. The sample collection methodologies have evolved with no significant change that could affect the quality of the data considered in this report into the currently used Hydrologic Procedures that support the Yucca Mountain Project-approved USGS Quality Assurance Program Plan. Consequently, for USGS data, the data collection methods, documentation, and results are reasonable and appropriate in view of standard practice at the time the data were collected. A small number of data sets were collected by organizations other than the USGS and were reviewed along with the other major ion and pH data using corroborating data methods. Hydrochemical studies reviewed in this qualification report indicate that the extent and quality of corroborating data are sufficient to support qualification of both USGS and non-USGS major ion and pH data for generalized hydrochemical studies. The corroborating data included other major ion and pH data, isotope data, and independent hydrological data. Additionally, the analytical adequacy of the major ion data was supported by a study of anion-cation charge balances. Charge balance errors for USGS and non-USGS data were under 10% and acceptable for all data. This qualification report addresses the specific major ion data sets selected to support the hydrochemical studies in Analysis/Model Report (AMR) S0040 and pH data used in AMRs U0100 and U0085. Based on a preponderance of evidence, these data are recommended to be qualified for inclusion in technical products in support of the Site Recommendation for generalized uses as described in this report.

C. WILSON; D.M. JENKINS; T. STEINBORN; R. WEMHEUER

2000-08-23T23:59:59.000Z

147

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

SciTech Connect (OSTI)

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

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.

2013-04-01T23:59:59.000Z

148

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

SciTech Connect (OSTI)

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

Herman, Connie C.

2013-09-30T23:59:59.000Z

149

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

SciTech Connect (OSTI)

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

Hariharan, Vasudevan; Lundin, Carl, W.

2005-09-30T23:59:59.000Z

150

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

SciTech Connect (OSTI)

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

Hariharan, Vasudevan; Lundin, Carl, D.

2005-09-30T23:59:59.000Z

151

(Final Draft) Superconducting  

E-Print Network [OSTI]

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

152

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

SciTech Connect (OSTI)

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.

Wohlgemuth, J. H.; Kurtz, S.

2011-02-01T23:59:59.000Z

153

Current industry standards and practices for qualification of NDE personnel -- What is performance demonstration telling us?  

SciTech Connect (OSTI)

This paper presents an overview of the most commonly used documents relating to qualification requirements for personnel who perform nondestructive examination (NDE), primarily ultrasonic (UT) examination in the oil and gas, petrochemical, and power industries. Nondestructive examination has been used for many years to ascertain the condition of a wide variety of components. An essential element in the effectiveness of nondestructive examination is the qualification of the personnel who are responsible for and who perform nondestructive examinations. One of the most effective methods of ascertaining the proficiency of equipment, procedures, and personnel is by a performance demonstration conducted on samples containing actual flaws. In the last 10 to 15 years, performance demonstrations have indicated the level of proficiency of personnel to be considerably lower than had been thought.

Kellerhall, R.A. [SubSea International Inc., Corpus Christi, TX (United States). NDE Services

1996-12-31T23:59:59.000Z

154

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

SciTech Connect (OSTI)

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.

Peeler, D.

2013-06-27T23:59:59.000Z

155

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

SciTech Connect (OSTI)

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.

NONE

1996-03-01T23:59:59.000Z

156

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

SciTech Connect (OSTI)

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.

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

2013-09-25T23:59:59.000Z

157

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

SciTech Connect (OSTI)

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.

Lofaro, R.; Lee, B.; Villaran, M. [Brookhaven National Lab., Upton, NY (United States); Gleason, J. [GLS Enterprises, Inc. (United States); Aggarwal, S. [Nuclear Regulatory Commission, Washington, DC (United States)

1995-12-31T23:59:59.000Z

158

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

Broader source: Energy.gov [DOE]

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

159

Qualification requirements of guided ultrasonic waves for inspection of piping in light water reactors  

SciTech Connect (OSTI)

It is anticipated that guided ultrasonic wave (GUW) techniques will eventually see widespread application in the nuclear power industry as there are several near-term and future needs that could benefit from the availability of GUW technologies. Already, GUW techniques are receiving consideration for inspecting buried piping at nuclear power plants and future applications may include several Class 1 and 2 components. To accept the results of a nondestructive examination of safety critical components, the U.S. Nuclear Regulatory Commission requires that the examinations be performed using qualified equipment, personnel, and procedures. As the use of GUW techniques becomes more frequent, qualification may be required. Performance demonstration has been the approach to qualifying conventional NDE methods in the nuclear power industry. This paper highlights potential issues and research needs associated with facilitating GUW qualification for the nuclear power industry. Parametric studies of essential inspection parameters are necessary to understand their influence on inspection performance. The large volume sampling capability introduces several challenges for qualifying GUW techniques including the quantification of performance, potential interference caused by the presence of multiple flaws in the inspection region, and the practicality of manufacturing several large qualification specimens. Computer simulation may have a significant role in reducing the experimental burden associated with qualifying GUW techniques for nuclear power plant examinations.

Meyer, R. M.; Ramuhalli, P.; Doctor, S. R. [Applied Physics, Pacific Northwest National Laboratory, Richland, WA 99352 (United States); Bond, L. J. [Center for Nondestructive Evaluation, Iowa State University, Ames, IA 50011 (United States)

2013-01-25T23:59:59.000Z

160

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

SciTech Connect (OSTI)

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.

NONE

1996-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "qualification final" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

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

SciTech Connect (OSTI)

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

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.

2012-05-16T23:59:59.000Z

162

Functional issues and environmental qualification of digital protection systems of advanced light-water nuclear reactors  

SciTech Connect (OSTI)

Issues of obsolescence and lack of infrastructural support in (analog) spare parts, coupled with the potential benefits of digital systems, are driving the nuclear industry to retrofit analog instrumentation and control (I&C) systems with digital and microprocessor-based systems. While these technologies have several advantages, their application to safety-related systems in nuclear power plants raises key issues relating to the systems` environmental qualification and functional reliability. To bound the problem of new I&C system functionality and qualification, the authors focused this study on protection systems proposed for use in ALWRs. Specifically, both functional and environmental qualification issues for ALWR protection system I&C were addressed by developing an environmental, functional, and aging data template for a protection division of each proposed ALWR design. By using information provided by manufacturers, environmental conditions and stressors to which I&C equipment in reactor protection divisions may be subjected were identified. The resulting data were then compared to a similar template for an instrument string typically found in an analog protection division of a present-day nuclear power plant. The authors also identified fiber-optic transmission systems as technologies that are relatively new to the nuclear power plant environment and examined the failure modes and age-related degradation mechanisms of fiber-optic components and systems. One reason for the exercise of caution in the introduction of software into safety-critical systems is the potential for common-cause failure due to the software. This study, however, approaches the functionality problem from a systems point of view. System malfunction scenarios are postulated to illustrate the fact that, when dealing with the performance of the overall integrated system, the real issues are functionality and fault tolerance, not hardware vs. software.

Korsah, K.; Clark, R.L.; Wood, R.T. [Oak Ridge National Lab., TN (United States)

1994-04-01T23:59:59.000Z

163

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

SciTech Connect (OSTI)

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.

McCoskey, Jacob K.

2014-01-22T23:59:59.000Z

164

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

SciTech Connect (OSTI)

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.

Oji, L. N.

2013-03-07T23:59:59.000Z

165

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

SciTech Connect (OSTI)

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.

Peters, T.; Fink, S.

2012-03-26T23:59:59.000Z

166

Quality Assurance Program Plan for AGR Fuel Development and Qualification Program  

SciTech Connect (OSTI)

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.

W. Ken Sowder

2004-02-01T23:59:59.000Z

167

Problems and Tasks of TRAINING at Courses for Enhancement of Qualification in the Radioactive Waste Management Area  

SciTech Connect (OSTI)

Requirements to the professional competence of the personnel engaged in the area of the radioactive waste management are increased. Higher school cannot supply the branch with the qualified personnel; therefore special attention should be given to the system of staff retraining and to the increase of their qualification. In that paper the analysis of SIA ''Radon'' experience on the organization and carrying out training at courses of qualification improvement is represented. The main criterion of the analysis is the research of an education efficiency. Also here the basic directions of the training process improving are submitted as well as the requirements that should be considered when forming the teaching staff and trainees groups.

Sobolev, I. A.; Dmitriev, S. A.; Batyukhnova, O. G.; Shcherbatova, T. D.; Ojovan, M. I.; Arustamov, A. E.

2002-02-25T23:59:59.000Z

168

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

SciTech Connect (OSTI)

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.

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

2012-08-01T23:59:59.000Z

169

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

SciTech Connect (OSTI)

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.

NONE

1993-02-01T23:59:59.000Z

170

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

SciTech Connect (OSTI)

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 position. DOE Order 5480-20, ``Personnel Selection, Qualification, Training, and Staffing Requirements at DOE Reactor and Non-Reactor Nuclear Facilities,`` states that only Category A reactors must use shift technical advisor position. 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 presented based on the premise that the trainee has not completed any facility-specific training other than general employee training.

Not Available

1993-02-01T23:59:59.000Z

171

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

SciTech Connect (OSTI)

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.

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

2013-08-01T23:59:59.000Z

172

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

SciTech Connect (OSTI)

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.

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

2012-08-01T23:59:59.000Z

173

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

SciTech Connect (OSTI)

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

Edwards, T; Mahannah, R.

2011-07-05T23:59:59.000Z

174

" Million Housing Units, Final...  

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

9 Fuels Used and End Uses in Homes in Midwest Region, Divisions, and States, 2009" " Million Housing Units, Final" ,,"Midwest Census Region" ,,,"East North Central Census...

175

" Million Housing Units, Final...  

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

1 Computers and Other Electronics in Homes in West Region, Divisions, and States, 2009" " Million Housing Units, Final" ,,"West Census Region" ,,,"Mountain Census...

176

" Million Housing Units, Final...  

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

0 Computers and Other Electronics in Homes in South Region, Divisions, and States, 2009" " Million Housing Units, Final" ,,"South Census Region" ,,,"South Atlantic Census...

177

" Million Housing Units, Final...  

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

9 Computers and Other Electronics in Homes in Midwest Region, Divisions, and States, 2009" " Million Housing Units, Final" ,,"Midwest Census Region" ,,,"East North Central Census...

178

" Million Housing Units, Final...  

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

8 Computers and Other Electronics in Homes in Northeast Region, Divisions, and States, 2009" " Million Housing Units, Final" ,,"Northeast Census Region" ,,,"New England Census...

179

" Million Housing Units, Final...  

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

1 Air Conditioning in Homes in West Region, Divisions, and States, 2009" " Million Housing Units, Final" ,,"West Census Region" ,,,"Mountain Census Division",,,"Pacific Census...

180

" Million Housing Units, Final...  

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

8 Air Conditioning in Homes in Northeast Region, Divisions, and States, 2009" " Million Housing Units, Final" ,,"Northeast Census Region" ,,,"New England Census Division",,,"Middle...

Note: This page contains sample records for the topic "qualification final" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

" Million Housing Units, Final...  

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

0 Air Conditioning in Homes in South Region, Divisions, and States, 2009" " Million Housing Units, Final" ,,"South Census Region" ,,,"South Atlantic Census Division",,,,,,"East...

182

" Million Housing Units, Final"  

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

9 Air Conditioning in Homes in Midwest Region, Divisions, and States, 2009" " Million Housing Units, Final" ,,"Midwest Census Region" ,,,"East North Central Census...

183

National Science Bowl Finals  

SciTech Connect (OSTI)

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

2010-05-03T23:59:59.000Z

184

" Million Housing Units, Final...  

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

9 Water Heating in U.S. Homes in Midwest Region, Divisions, and States, 2009" " Million Housing Units, Final" ,,"Midwest Census Region" ,,,"East North Central Census...

185

" Million Housing Units, Final...  

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

0 Water Heating in U.S. Homes in South Region, Divisions, and States, 2009" " Million Housing Units, Final" ,,"South Census Region" ,,,"South Atlantic Census Division",,,,,,"East...

186

" Million Housing Units, Final...  

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

11 Water Heating in U.S. Homes in West Region, Divisions, and States, 2009" " Million Housing Units, Final" ,,"West Census Region" ,,,"Mountain Census Division",,,"Pacific...

187

" Million Housing Units, Final...  

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

8 Water Heating in U.S. Homes in Northeast Region, Divisions, and States, 2009" " Million Housing Units, Final" ,,"Northeast Census Region" ,,,"New England Census...

188

DOE Final Report  

SciTech Connect (OSTI)

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.

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

2014-01-08T23:59:59.000Z

189

Space: the final frontier  

E-Print Network [OSTI]

Edited by Markus Eichhorn frontiers of biogeography 6.2,6596 Space: the final frontier Spatial Simulation: Exploringpoints in some places, but frontiers of biogeography 6.2,

Stoll, Peter

2014-01-01T23:59:59.000Z

190

National Science Bowl Finals  

ScienceCinema (OSTI)

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

None

2010-09-01T23:59:59.000Z

191

Wellcome Trust SUBMISSION OF EVIDENCE Wellcome Trust response to Department for Education: Reforming Key Stage 4 qualifications  

E-Print Network [OSTI]

: Reforming Key Stage 4 qualifications December 2012 Department for Education: Reforming Key Stage 4 science skills. 2. We are pleased to have the opportunity to respond to the consultation on reforms to Key consultations on the reform to curriculum and assessment at various stages of schooling. There is an opportunity

Rambaut, Andrew

192

Final Draft ENVIRONMENTAL ASSESSMENT  

E-Print Network [OSTI]

the anticipated completion of the Constellation Programmatic Environmental Impact Statement in June 2008Final Draft ENVIRONMENTAL ASSESSMENT FOR THE CONSTRUCTION, MODIFICATION, AND OPERATION OF THREE CENTER, FL 32899 February 2007 #12;THIS PAGE INTENTIONALLY LEFT BLANK #12;FINAL DRAFT DRAFT ENVIRONMENTAL

Waliser, Duane E.

193

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

SciTech Connect (OSTI)

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

Edwards, T.; Mahannah, R.

2011-07-05T23:59:59.000Z

194

Data Qualification Report: Pore Water Data for Use on the Yucca Mountain Project  

SciTech Connect (OSTI)

Pore water data associated with Data Tracking Number (DTN) No.LL990702804244.100 are referenced in the Analysis and Model Reports (AMRs) prepared to support the Site Recommendation in determining the suitability of the Yucca Mountain, Nevada as a repository for high-level nuclear waste. It has been determined, in accordance with procedure AP-3.15Q Rev. 1, ICN 1, ''Managing Technical Product Inputs'', Attachment 6 , that the DTN-referenced data are used in AMRs that provide a direct calculation of ''Principal Factors'' for the Post-closure Safety Case or Potentially Disruptive Processes or Events. Therefore, in accordance with the requirements of procedure AP-SIII.2Q, Rev 0, ICN 2, ''Qualification of Unqualified Data and the Documentation of Rationale for Accepted Data'', Section 5.3.1 .a, a Data Qualification Report has been prepared for submittal to the Assistant Manager, Office of Project Execution for concurrence. This report summarizes the findings of the Data Qualification Team assembled to evaluate unqualified ''pore water data'' represented by DTN No. LL990702804244.100. This DTN is currently used in the following AMRs: Drift-Scale Coupled Processes (DST and THC Seepage) Models (CRWMS M&O 2000a), Environment of the Surfaces of the Drip Shield and Waste Package Outer Barrier (CRWMS M&O 2000b), and Engineered Barrier System: Physical and Chemical Environment Model (CRWMS M&O 2000c). Mineral composition of pore water submitted to the Technical Data Management System (TDMS) using the subject DTN were acquired data from the analysis pore water samples sent to Lawrence Livermore National Laboratory's (LLNL) by UFA Ventures, Inc. and analyzed by LLNL's Analytical Sciences/Analytical and Nuclear Chemistry Division (ASD). The purpose and scope of the AMRs that reference the subject DTN and the potential application of pore water data is described below. These AMRs use only that data associated with the specific samples: ESF-HD-PERM-1, ESF-HD-PERM-2, and ESF-HD-PERM-3. The data for these samples represents a subset of the data identified as DTN No. LL990702804244.100.

H. Miller; R. Monks; C. Warren; W. Wowak

2000-06-09T23:59:59.000Z

195

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

SciTech Connect (OSTI)

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.

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

2013-07-08T23:59:59.000Z

196

Fabrication of specimens with controlled flaws for procedure development and personnel training and qualification  

SciTech Connect (OSTI)

Over the years, instances of service-induced flaws in vessel and piping components have prompted many utilities to acquire full-scale mockups to demonstrate the performance of nondestructive evaluation (NDE) procedures. Also, the newly invoked Appendix 8 requirement to the 1989 Section 11 ASME Code requires qualification of equipment, procedures, and personnel utilizing full-scale test specimens with actual flaws. This has increased the need for flaws that can be produced and accurately controlled in various test specimens. The typical service-induced flaws may consist of one of the following, depending on the material type and service conditions: mechanical fatigue; thermal fatigue; intergranular stress-corrosion (IGSC) cracking; and weld-induced flaws (during manufacture) such as slag, porosity, or incomplete fusion.

Edwards, R.L.; Watson, P.D.; Gruber, G.J. [Southwest Research Inst., San Antonio, TX (United States)

1994-12-31T23:59:59.000Z

197

DATA QUALIFICATION REPORT: WATER-LEVEL DATA FROM THE NYE COUNTY EARLY WARNING DRILLING PROGRAM  

SciTech Connect (OSTI)

The objective of this work is to evaluate unqualified, water-level data gathered under the Nye County Early Warning Drilling Program (EWDP) and to determine whether the status of the data should be changed to ''qualified'' data in accordance with AP-SIII.2Q (Qualification of Unqualified Data and the Documentation of Rationale for Accepted Data). The corroboration method (as defined in Attachment 2 of AP-SIII.2Q) was implemented to qualify water-level data from Nye County measurements obtained directly from the Nye County Nuclear Waste Repository Program Office (NWRPO). Comparison of United States Geological Survey (USGS) measurements contained in DTN GS990608312312.003 with the Nye County water-level data has shown that the differences in water-level altitudes for the same wells are significantly less than 1 meter. This is an acceptable finding. Evaluation and recommendation criteria have been strictly applied to qualify Nye County measurements of water levels in selected wells measured by the USGS. However, the process of qualifying measured results by corroboration also builds confidence that the Nye County method for measurement of water levels is adequate for the intended use of the data (which is regional modeling). Therefore, it is reasonable to extend the term of ''qualified'' to water-level measurements in the remaining Nye County Phase I wells on the basis that the method has been shown to produce adequate results for the intended purpose of supporting large-scale modeling activities for the Yucca Mountain Project (YMP). The Data Qualification Team recommends the Nye County, water-level data contained in Appendix D of this report be designated as ''qualified''. These data document manual measurements of water-levels in eight (8) EWDP Phase I drillholes that were obtained prior to the field installation of continuous monitoring equipment.

F. H. Dove, P. Sanchez, and L. Saraka

2000-04-21T23:59:59.000Z

198

YFTB_final_rep_FINAL2  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption byAbout SRNL Home SRNLSecurityNationalComplex ers earnFinal

199

" Million Housing Units, Final...  

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

6 Televisions in U.S. Homes, by Climate Region, 2009" " Million Housing Units, Final" ,,"Climate Region2" ,"Total U.S.1 (millions)" ,,"Very Cold","Mixed- Humid","Mixed-Dry"...

200

Aurora final report  

SciTech Connect (OSTI)

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)

Robert, Dross; Amedeo, Conti

2013-12-06T23:59:59.000Z

Note: This page contains sample records for the topic "qualification final" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

" Million Housing Units, Final...  

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

" Million Housing Units, Final" ,,"Climate Region2" ,"Total U.S.1 (millions)" ,,"Very Cold","Mixed- Humid","Mixed-Dry" "Fuels Used and End Uses",,"Cold",,"Hot-Dry","Hot-Humid...

202

" Million Housing Units, Final...  

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

Computers and Other Electronics in U.S. Homes, by Housing Unit Type, 2009" " Million Housing Units, Final" ,,"Housing Unit Type" ,,"Single-Family Units",,"Apartments in Buildings...

203

" Million Housing Units, Final...  

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

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

204

" Million Housing Units, Final...  

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

7 Computers and Other Electronics in U.S. Homes, by Census Region, 2009" " Million Housing Units, Final" ,,"Census Region" ,"Total U.S.1 (millions)" ,,"Northeast","Midwest","South"...

205

" Million Housing Units, Final...  

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

2 Computers and Other Electronics in U.S. Homes, by OwnerRenter Status, 2009" " Million Housing Units, Final" ,,,,"Housing Unit Type" ,,,,"Single-Family Units",,,,"Apartments in...

206

" Million Housing Units, Final"  

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

5 Computers and Other Electronics in U.S. Homes, by Household Income, 2009" " Million Housing Units, Final" ,,"Household Income" ,"Total U.S.1 (millions)",,,"Below Poverty...

207

final.tex  

E-Print Network [OSTI]

Final Exam Math 6121A (Algebra I) Dec 13, 2000. Time: 2hrs 50 min. Attempt all questions. You are advised to spend not more than one hour on Part A.

208

" Million Housing Units, Final...  

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

4 Air Conditioning in U.S. Homes, by Number of Household Members, 2009" " Million Housing Units, Final" ,,"Number of Household Members" ,"Total U.S.1 (millions)" ,,,,,,"5 or More...

209

" Million Housing Units, Final...  

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

7 Air Conditioning in U.S. Homes, by Census Region, 2009" " Million Housing Units, Final" ,,"Census Region" ,"Total U.S.1 (millions)" ,,"Northeast","Midwest","South","West" "Air...

210

" Million Housing Units, Final...  

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

Air Conditioning in U.S. Homes, by Housing Unit Type, 2009" " Million Housing Units, Final" ,,"Housing Unit Type" ,,"Single-Family Units",,"Apartments in Buildings With" ,"Total...

211

" Million Housing Units, Final...  

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

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

212

" Million Housing Units, Final"  

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

5 Air Conditioning in U.S. Homes, by Household Income, 2009" " Million Housing Units, Final" ,,"Household Income" ,"Total U.S.1 (millions)",,,"Below Poverty Line2" ,,"Less...

213

" Million Housing Units, Final...  

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

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

214

" Million Housing Units, Final...  

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

3 Appliances in U.S. Homes, by Year of Construction, 2009" " Million Housing Units, Final" ,,"Year of Construction" ,"Total U.S.1 (millions)" ,,"Before 1940","1940 to 1949","1950...

215

" Million Housing Units, Final...  

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

3 Televisions in U.S. Homes, by Year of Construction, 2009" " Million Housing Units, Final" ,,"Year of Construction" ,"Total U.S.1 (millions)" ,,"Before 1940","1940 to 1949","1950...

216

" Million Housing Units, Final...  

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

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

217

" Million Housing Units, Final...  

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

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

218

" Million Housing Units, Final...  

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

5 Water Heating in U.S. Homes, by Household Income, 2009" " Million Housing Units, Final" ,,"Household Income" ,"Total U.S.1 (millions)",,,"Below Poverty Line2" ,,"Less than...

219

" Million Housing Units, Final...  

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

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

220

" Million Housing Units, Final...  

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

6 Water Heating in U.S. Homes, by Climate Region, 2009" " Million Housing Units, Final" ,,"Climate Region2" ,"Total U.S.1 (millions)" ,,"Very Cold","Mixed- Humid","Mixed-Dry"...

Note: This page contains sample records for the topic "qualification final" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

" Million Housing Units, Final...  

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

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

222

" Million Housing Units, Final...  

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

7 Water Heating in U.S. Homes, by Census Region, 2009" " Million Housing Units, Final" ,,"Census Region" ,"Total U.S.1 (millions)" ,,"Northeast","Midwest","South","West" "Water...

223

" Million Housing Units, Final...  

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

4 Water Heating in U.S. Homes, by Number of Household Members, 2009" " Million Housing Units, Final" ,,"Number of Household Members" ,"Total U.S.1 (millions)" ,,,,,,"5 or More...

224

" Million Housing Units, Final...  

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

Housing Units, Final" ,,"Household Income" ,"Total U.S.1 (millions)",,,"Below Poverty Line2" ,,"Less than 20,000","20,000 to 39,999","40,000 to 59,999","60,000 to...

225

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

SciTech Connect (OSTI)

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.

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

2013-09-19T23:59:59.000Z

226

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

SciTech Connect (OSTI)

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).

Peters, T.; Fink, S.

2012-04-24T23:59:59.000Z

227

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

SciTech Connect (OSTI)

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).

Michael L. Abbott; Keith A. Daum

2011-08-01T23:59:59.000Z

228

Final Technical Report  

SciTech Connect (OSTI)

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.

Gilbert, Chris [Altamont Environmental, Inc.] [Altamont Environmental, Inc.

2014-11-13T23:59:59.000Z

229

Final Report Sustainability at  

E-Print Network [OSTI]

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

Escher, Christine

230

Final Scientific/Technical Report  

SciTech Connect (OSTI)

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

Troxell, W; Batchelor, A

2012-11-28T23:59:59.000Z

231

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

SciTech Connect (OSTI)

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).

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

2011-09-01T23:59:59.000Z

232

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

SciTech Connect (OSTI)

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).

Peters, T.; Fink, S.

2011-06-22T23:59:59.000Z

233

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

SciTech Connect (OSTI)

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.

Unknown

2002-02-08T23:59:59.000Z

234

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

SciTech Connect (OSTI)

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.

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

2014-06-01T23:59:59.000Z

235

Final Technical Report  

SciTech Connect (OSTI)

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.

Maxwell, Mike, J., P.E.

2012-08-30T23:59:59.000Z

236

Sustainable energy Examen Final  

E-Print Network [OSTI]

Sustainable energy Examen Final 24 mai 2013 Consignes ­ Vous disposez de 2 heures 30. ­ N'oubliez pas de r´epondre `a chaque question sur des feuilles s´epar´ees et d'indiquer votre nom sur chaque feuille. ­ La r´eponse `a la question huit doit se faire en anglais et sur la derni`ere feuille de l

Ernst, Damien

237

SWERA_Final_Report  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia:FAQ < RAPID Jump to: navigation, searchVirginiaRooseveltVI Solar Power PlantCenter Final Report Country

238

Final Technical Report  

SciTech Connect (OSTI)

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.

Sobecky, Patricia A; Taillefert, Martial

2013-03-29T23:59:59.000Z

239

Final Notice of Violation  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAX POLICIES ANDIndustrialEnergyFinal FY 2009 NEUP RD Awards

240

Final Vitrification Melter Evaluation  

Office of Environmental Management (EM)

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241

Final Design RM  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power SystemsResourcesFLASH2011-11-OPAMFY 2007 TotalFinal Design Review Module March 2010 CD-0

242

FINAL TECHNICAL REPORT  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicy andExsolutionFES Committees of VisitorsASCRReal-time2 FINAL

243

FINAL TECHNICAL REPORT Department  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicy andExsolutionFES Committees of9, 2011 FINALOffice ofFINAL

244

Final Exam | Jefferson Lab  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicyFeasibilityField Office ProgramsFinal Exam November 30, 2008 In

245

Final FY 2002 PRS  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicyFeasibilityField Office ProgramsFinal Exam November 30, 2008

246

Final FY 2002 PRS  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicyFeasibilityField Office ProgramsFinal Exam November 30,

247

Final FY 2002 PRS  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicyFeasibilityField Office ProgramsFinal Exam November 30,29/kW-mo *

248

Final FY 2002 PRS  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicyFeasibilityField Office ProgramsFinal Exam November 30,29/kW-mo

249

Final Power Amplifier  

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

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250

Final_Report.indd  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicyFeasibilityField Office Final Tank Closure andREMEDIATE ANDEnergy

251

Final_Report.indd  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicyFeasibilityField Office Final Tank Closure andREMEDIATE

252

Final_Report.indd  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicyFeasibilityField Office Final Tank Closure andREMEDIATE Department

253

RPSEA Final Report  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared at 278, 298, and 323 K.OfficeNote:BEAMENV-39658RPSEA Final Report

254

DOE Laminar Final Report  

Office of Scientific and Technical Information (OSTI)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinan antagonist Journal Article: Crystal structureComposite-- Energy,Converting to5994DOE AwardFinal

255

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

SciTech Connect (OSTI)

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.

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

2013-08-08T23:59:59.000Z

256

Data Qualification Report: Precipitation Chloride Data for Use on the Yucca Mountain Project  

SciTech Connect (OSTI)

The data covered by this qualification report have been cited in analysis/model reports (AMRs) to support the Site Recommendation in determining the suitability of Yucca Mountain as a repository for high level nuclear waste. Those analyses cited both qualified and unqualified hydrochemical data. This report evaluates unqualified precipitation chloride data based on the pedigree of the data and within the context of supporting analyses on the Yucca Mountain Project (YMP). The following AMRs use the unqualified chloride data considered in this report: (1) AMR S0040, ''Geochemical and Isotopic Constraints on Groundwater Flow Directions, Mixing and Recharge at Yucca Mountain'' (ANL-NBS-HS-000021) (Kwicklis 2000)--an analysis of groundwater recharge rates, flow directions and velocities, and mixing proportions of water from different source areas based on groundwater geochemical and isotopic data. (2) AMR U0085, ''Analysis of Geochemical Data for the Unsaturated Zone'' (ANL-NBS-HS-000017) (Fabryka-Martin 2000)--identifies fluid geochemical parameters for the unsaturated zone, local precipitation, and surface water; discusses the occurrence and origins of fracture minerals; and presents a thermal history of the unsaturated zone. These data are being evaluated for inclusion in technical products to include AMRs and Process Modeling Reports (PMRs) that support the Site Recommendation and that may also be used to support the License Application. A finding that the precipitation chloride data are qualified means that the data are adequate for generalized use and can be appropriately used in a wide variety of applications, so long as consideration is given to limitations on the accuracy, precision and representativeness of the data for an intended use in a technical product.

C. Wilson

2000-09-30T23:59:59.000Z

257

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

SciTech Connect (OSTI)

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

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

2008-11-10T23:59:59.000Z

258

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

SciTech Connect (OSTI)

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.

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

2012-02-01T23:59:59.000Z

259

AIPM Final Report  

SciTech Connect (OSTI)

The final AIPM project report consists of six sections. Each section includes information on the original AIPM project and extension work on the high temperature design. The first section (1) provides an overview of the program and highlights the significant targets to meet at the end of the program. The next section (2) summarizes the significant technical accomplishments by the SEMIKRON AIPM team during the course of the project. Greater technical details are provided in a collection of all the quarterly reports which can be found in the appendix. Section three (3) presents some the more significant technical data collected from technology demonstrators. Section four (4) analyzes the manufacturing cost or economic aspects of producing 100,000 units/yr. Section five (5) describes the commercialization efforts of the AIPM technology into the automotive market. The last section (6) recommends follow on work that will build on the efforts and achievements of the AIPM program.

John Mookken

2006-06-30T23:59:59.000Z

260

DEWPOINT. Final report  

SciTech Connect (OSTI)

The DEWPOINT (Directed Energy POwer INTegration) program was aimed at providing the large amounts of electric power required for a laser or accelerator based in space, or on an aircraft or satellite platform. This is our final report on our efforts as a part of this program which was cancelled before completion. This report summarizes the entire scope of effort funded by this program. It also includes some related information on cryogenically cooled microchannel heatsinks which was funded internally by LLNL. Specifically, the DEWPOINT program was to provide the electrical power for the proposed Neutral Particle Beam weapon system of the Strategic Defense Initiative. The Neutral Particle Beam called for a space-based accelerator driven by radio frequency power sources. The radio frequency solid-state power amplifiers generate waste heat which must be dissipated.

Riddle, R.A.

1994-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "qualification final" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

FINAL/ SCIENTIFIC TECHNICAL REPORT  

SciTech Connect (OSTI)

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

McDonald, Henry; Singh, Suminderpal

2006-08-28T23:59:59.000Z

262

Final Progress Report  

SciTech Connect (OSTI)

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.

Josef Michl

2011-10-31T23:59:59.000Z

263

Final Scientific EFNUDAT Workshop  

ScienceCinema (OSTI)

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

None

2011-10-06T23:59:59.000Z

264

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

SciTech Connect (OSTI)

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

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

2013-02-25T23:59:59.000Z

265

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

SciTech Connect (OSTI)

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.

SAMS TL; EDGE JA; SWANBERG DJ; ROBBINS RA

2011-01-13T23:59:59.000Z

266

Literature review of environmental qualification of safety-related electric cables: Literature analysis and appendices. Volume 2  

SciTech Connect (OSTI)

In support of the US NRC Environmental Qualification (EQ) Research Program, a literature review was performed to identify past relevant work that could be used to help fully or partially resolve issues of interest related to the qualification of low-voltage electric cable. A summary of the literature reviewed is documented in Volume 1 of this report. In this, Volume 2 of the report, dossiers are presented which document the issues selected for investigation in this program, along with recommendations for future work to resolve the issues, when necessary. The dossiers are based on an analysis of the literature reviewed, as well as expert opinions. This analysis includes a critical review of the information available from past and ongoing work in thirteen specific areas related to EQ. The analysis for each area focuses on one or more questions which must be answered to consider a particular issue resolved. Results of the analysis are presented, along with recommendations for future work. The analysis is documented in the form of a dossier for each of the areas analyzed.

Lofaro, R.; Bowerman, B.; Carbonaro, J. [Brookhaven National Lab., Upton, NY (United States)] [and others

1996-04-01T23:59:59.000Z

267

Long-Term Materials-Test Program. Annual report and Qualification Test Plan, October 1979-September 1980  

SciTech Connect (OSTI)

Progress made on the Long Term Materials Test Program during its first year is summarized and the test planning required to perform the Qualification Test is documented. The objective of the Qualification Test is to check out the proper functioning of the Test Rig and to demonstrate its capability to produce a representative PFB off-gas environment for long term candidate-material testing. During the first year of the program, the project has progressed from the concept stage to the start of construction. Ninety-five percent of the equipment has been ordered and renovations to accommodate the test rig have been initiated at the Malta Site. The initial effort focused on the test rig configuration and selection of the candidate turbine materials. The preliminary design phase was officially culminated by the presentation and acceptance of the Preliminary Operations Plan to DOE during April 1980. By mid-June, 1981, the design of the major components was substantially complete allowing a detailed external design review to be performed. The design was accepted, and purchase orders for the major components were placed. In parallel with the design effort, two materials-screening tests have been initiated. One thousand hours of testing on the oil-fired small burner rig and the first 250-h segment on the erosion/corrosion simulator has been completed.

None

1981-04-01T23:59:59.000Z

268

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

SciTech Connect (OSTI)

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

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

2013-05-01T23:59:59.000Z

269

Final Technical Report  

SciTech Connect (OSTI)

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.

Alexander Pigarov

2012-06-05T23:59:59.000Z

270

Final Technical Report  

SciTech Connect (OSTI)

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.

Velasco, Mayda [Northwestern University] [Northwestern University

2013-11-01T23:59:59.000Z

271

Final Report to DOE  

SciTech Connect (OSTI)

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.

Ismail Gultepe

2012-05-15T23:59:59.000Z

272

Final Technical Report  

SciTech Connect (OSTI)

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.

Alexander Fridman

2005-06-01T23:59:59.000Z

273

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

SciTech Connect (OSTI)

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.

Sun, K. X.

2011-05-31T23:59:59.000Z

274

2014 : Qualification aux fonctions de matre de confrences (Section CNU 06 Sciences de gestion) 2013 : Doctorat en Sciences de gestion -IAE de Bretagne Occidentale -Laboratoire ICI EA2652  

E-Print Network [OSTI]

2014 : Qualification aux fonctions de maître de conférences (Section CNU 06 ­ Sciences de gestion) 2013 : Doctorat en Sciences de gestion - IAE de Bretagne Occidentale - Laboratoire ICI EA2652 Sujet de Bretagne Occidentale 2007 : Licence de Droit, option économie-gestion (mention B), Université de

Brest, Université de

275

SMITH, GLEN. Bond Characteristics and Qualifications of Adhesives for Marine Applications and Steel Pipe Repair. (Under the direction of Dr. Sami Rizkalla.)  

E-Print Network [OSTI]

designs using new materials. Adhesives that bond metals, plastics, FRP and other materials have been used for marine application and repair of steel pipeline. #12;BOND CHARACTERISTICS AND QUALIFICATIONS OF ADHESIVES of Science Department of Civil, Construction, and Environmental Engineering Raleigh 2005 APPROVED BY

276

LIVE_NSB_final.wmv  

SciTech Connect (OSTI)

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

2010-05-12T23:59:59.000Z

277

LIVE_NSB_final.wmv  

ScienceCinema (OSTI)

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

None

2010-09-01T23:59:59.000Z

278

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

SciTech Connect (OSTI)

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

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

2012-05-11T23:59:59.000Z

279

ASEDRA Evaluation Final Report.  

SciTech Connect (OSTI)

The performance of the Advanced Synthetically Enhanced Detector Resolution Algorithm (ASEDRA) was evaluated by performing a blind test of 29 sets of gamma-ray spectra that were provided by DNDO. ASEDRA is a post-processing algorithm developed at the Florida Institute of Nuclear Detection and Security at the University of Florida (UF/FINDS) that extracts char-acteristic peaks in gamma-ray spectra. The QuickID algorithm, also developed at UF/FINDS, was then used to identify nuclides based on the characteristic peaks generated by ASEDRA that are inferred from the spectra. The ASEDRA/QuickID analysis results were evaluated with respect to the performance of the DHSIsotopeID algorithm, which is a mature analysis tool that is part of the Gamma Detector Response and Analysis Software (GADRAS). Data that were used for the blind test were intended to be challenging, and the radiation sources included thick shields around the radioactive materials as well as cargo containing naturally occurring radio-active materials, which masked emission from special nuclear materials and industrial isotopes. Evaluation of the analysis results with respect to the ground truth information (which was provided after the analyses were finalized) showed that neither ASEDRA/QuickID nor GADRAS could identify all of the radiation sources correctly. Overall, the purpose of this effort was primarily to evaluate ASEDRA, and GADRAS was used as a standard against which ASEDRA was compared. Although GADRAS was somewhat more accurate on average, the performance of ASEDRA exceeded that of GADRAS for some of the unknowns. The fact that GADRAS also failed to identify many of the radiation sources attests to the difficulty of analyzing the blind-test data that were used as a basis for the evaluation. This evaluation identified strengths and weaknesses of the two analysis approaches. The importance of good calibration data was also clear because the performance of both analysis methods was impeded by the inability to define the energy calibration accurately. Acronyms ACHIP adaptive chi-processed ASEDRA Advanced Synthetically Enhanced Detector Resolution Algorithm DNDO Domestic Nuclear Detection Office DRFs Detector Response Functions FINDS Florida Institute of Nuclear Detection and Security FWHM full-width half-maximum GADRAS Gamma Detector Response Analysis Software GUI graphical user interface HEU highly enriched uranium HPGe high purity germanium ID identification NaI Sodium iodide NNSA National Nuclear Security Administration NORM Naturally Occurring Radioactive Materials ppm parts per million SNL Sandia National Laboratories UF University of Florida WGPu weapons-grade plutonium

Mitchell, Dean James; Detwiler, Dr. Rebecca; Sjoden, Dr, Glenn E.

2008-09-01T23:59:59.000Z

280

Danish Energy Authority Final Report  

E-Print Network [OSTI]

Danish Energy Authority Final Report Implementation of the EU directive on the energy performance of buildings: Development of the Latvian Scheme for energy auditing of buildings and inspection of boilers Final Report Implementation of the EPB directive in Latvia: Development of the Latvian Scheme for energy

Note: This page contains sample records for the topic "qualification final" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

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

SciTech Connect (OSTI)

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

David Petti

2014-06-01T23:59:59.000Z

282

Final Uranium Leasing Program Programmatic Environmental Impact...  

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

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

283

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

SciTech Connect (OSTI)

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

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

2011-07-08T23:59:59.000Z

284

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

SciTech Connect (OSTI)

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.

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

2013-03-18T23:59:59.000Z

285

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

SciTech Connect (OSTI)

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.

Michael L. Abbott; Binh T. Pham

2012-06-01T23:59:59.000Z

286

Floor response spectra for seismic qualification of Kozloduy VVER 440-230 NPP  

SciTech Connect (OSTI)

In this paper the floor response spectra generation methodology for Kozloduy NPP, Unit 1-2 of VVER 440-230 is presented. The 2D coupled soil-structure interaction models are used combined with a simplified correction of the final results for accounting of torsional effects. Both time history and direct approach for in-structure spectra generation are used and discussion of results is made.

Kostov, M.K. [Bulgarian Academy of Sciences, Sofia (BG). Central Lab. for Seismic Mechanics and Earthquake Engineering; Ma, D.C. [Argonne National Lab., IL (United States); Prato, C.A. [Univ. of Cordoba (AR); Stevenson, J.D. [Stevenson and Associates, Cleveland, OH (US)

1993-08-01T23:59:59.000Z

287

Final Report: Axion "Roadmap" Workshop  

SciTech Connect (OSTI)

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.

Rosenberg, Leslie J

2013-03-19T23:59:59.000Z

288

Reactor physics project final report  

E-Print Network [OSTI]

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

Driscoll, Michael J.

1970-01-01T23:59:59.000Z

289

Review Sheet for Final Exam  

E-Print Network [OSTI]

REVIEW FOR FINAL EXAM MA 139000. 36. 5 people can paint 3 rooms in 6 hours. How many rooms can 15 people paint in half a day? 37. Which of the ...

2015-01-05T23:59:59.000Z

290

Danish Energy Authority Final report  

E-Print Network [OSTI]

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

291

Stanford Geothermal Program Final Report  

E-Print Network [OSTI]

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

Stanford University

292

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

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism inS-4500IIVasudhaSurface.Laboratory30, 2014WIPP'sFinal ProposalFinal

293

An evaluation of methodology for seismic qualification of equipment, cable trays, and ducts in ALWR plants by use of experience data  

SciTech Connect (OSTI)

Advanced Reactor Corporation (ARC) has developed a methodology for seismic qualification of equipment, cable trays and ducts in Advanced Light Water Reactor plants. A Panel (members of which acted as individuals) supported by the Office of Nuclear Regulatory Research of the Nuclear Regulatory Commission has evaluated this methodology. The review approach and observations are included in this report. In general, the Panel supports the ARC methodology with some exceptions and provides recommendations for further improvements. 26 refs., 10 figs., 1 tab.

Bandyopadhyay, K.K.; Kana, D.D.; Kennedy, R.P.; Schiff, A.J.

1997-07-01T23:59:59.000Z

294

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

SciTech Connect (OSTI)

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

D. P. Blanchard; R. W. Youngblood

2014-06-01T23:59:59.000Z

295

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

SciTech Connect (OSTI)

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.

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

2013-05-31T23:59:59.000Z

296

MPO B593110 - Final Report  

SciTech Connect (OSTI)

National Security Technologies, LLC (NSTec) shall provide one (1) Mechanical Engineer to support the Linear Collider Subsystem Development Program at Lawrence Livermore National Security, LLC (LLNS). The NSTec Mechanical Engineer's efforts will include engineering, design, and drawing support for the Vacuum Seal Test. NSTec will also provide a final report of the setup and input to LLNL's project management on project status. The NSTec Mechanical Engineer's efforts will also include engineering, design, and drawing support to the conceptual design for manufacturing of the Flux Concentrator Magnet. NSTec will also contribute to LLNS's final report on the Flux Concentrator Magnet. The deliverables are drawings, sketches, engineering documents, and final reports delivered to the LLNS Technical Representative.

Brooksby, C

2011-07-25T23:59:59.000Z

297

MAST 1 purchased products--components. Final report  

SciTech Connect (OSTI)

AlliedSignal Inc., Kansas City Division, the production agency, was provided with funding to acquire purchased product components in support of the MAST (Multi-Application Surety Technology) Program. Implementation efforts, closing procurement status, and proposals for improvements in the procurement process are presented. The intent of this project was to fund the Purchased Product Team`s traditional procurement of components, with significantly reduced flowtime, in accordance with the Qualification Evaluation System, and to exercise the system to the extent possible. When funding was reduced, it became obvious that full implementation of the Qualification Evaluation System could not be achieved due to limited resources.

Brown, R.J.

1995-10-01T23:59:59.000Z

298

Final Meeting Summary Page 1  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicyFeasibilityField Office ProgramsFinal ExamDecember 11, 2014 FINAL

299

Final Meeting Summary Page 1  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicyFeasibilityField Office ProgramsFinal7, 2014 FINAL MEETING SUMMARY

300

Final Meeting Summary Page 1  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicyFeasibilityField Office ProgramsFinal7, 2014 FINAL MEETING

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301

Final Meeting Summary Page 1  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicyFeasibilityField Office ProgramsFinal7, 2014 FINAL MEETINGRiver

302

Final Meeting Summary Page 1  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicyFeasibilityField Office ProgramsFinal7, 2014 FINAL

303

Final Meeting Summary Page 1  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicyFeasibilityField Office ProgramsFinal7, 2014November 7, 2012 FINAL

304

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...

305

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

SciTech Connect (OSTI)

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

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

2012-08-22T23:59:59.000Z

306

Texas Transportation Poll Final report  

E-Print Network [OSTI]

Texas Transportation Poll Final report PRC 14-16-F #12;2 Texas Transportation Poll Texas A&M Transportation Institute PRC 14-16-F September 2014 Authors Chris Simek Tina Geiselbrecht #12;3 Table of Contents .......................................................................................................................... 8 Transportation Funding

307

FINAL REPORT CANYON AND SLOPE  

E-Print Network [OSTI]

and the influence of canyons on slope cur- rents ; f) identification of communities which may be affected by oil#12;FINAL REPORT CANYON AND SLOPE PROCESSES STUDY VOLUME I EXECUTIVE S(2@lARY Prepared for United and provides diverse habi- tats for biological communities. In the Mid- and North Atlantic Region, canyons have

Mathis, Wayne N.

308

MINIMARS conceptual design: Final report  

SciTech Connect (OSTI)

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)

Lee, J.D. (ed.)

1986-09-01T23:59:59.000Z

309

Stanford Geothermal Program Final Report  

E-Print Network [OSTI]

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

Stanford University

310

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

SciTech Connect (OSTI)

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.

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

2011-03-14T23:59:59.000Z

311

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

SciTech Connect (OSTI)

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.

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

2014-06-01T23:59:59.000Z

312

INITIAL IRRADIATION OF THE FIRST ADVANCED GAS REACTOR FUEL DEVELOPMENT AND QUALIFICATION EXPERIMENT IN THE ADVANCED TEST REACTOR  

SciTech Connect (OSTI)

The United States Department of Energy’s Advanced Gas Reactor (AGR) Fuel Development and Qualification Program will be irradiating eight separate tri-isotopic (TRISO) particle fuel (in compact form) experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). These irradiations and fuel development are being accomplished to support development of the next generation reactors in the United States. The ATR has a long history of irradiation testing in support of reactor development and the INL has been designated as the United States Department of Energy’s lead laboratory for nuclear energy development. The ATR is one of the world’s premiere test reactors for performing long term, high flux, and/or large volume irradiation test programs. These AGR fuel experiments will be irradiated over the next ten years to demonstrate and qualify new particle fuel for use in high temperature gas reactors. The experiments, which will each consist of six separate capsules, will be irradiated in an inert sweep gas atmosphere with individual on-line temperature monitoring and control for each capsule. The swept gas will also have on-line fission product monitoring to track performance of the fuel in each individual capsule during irradiation.

S. Blaine Grover; David A. Petti

2007-09-01T23:59:59.000Z

313

The Mission and Technology of a Gas Dynamic Trap Neutron Source for Fusion Material and Component Testing and Qualification  

SciTech Connect (OSTI)

This report summarizes discussions and conclusions of the workshop to 'Assess The Mission and Technology of a Gas Dynamic Trap Neutron Source for Fusion Material and Component Testing and Qualification'. The workshop was held at LBNL, Berkeley, CA on March 12, 2009. Most workshop attendees have worked on magnetic mirror systems, several have worked on similar neutron source designs, and others are knowledgeable of materials, fusion component, and neutral beams The workshop focused on the gas dynamic trap DT Neutron Source (DTNS) concept being developed at the Budker Institute of Nuclear Physics (BINP) in Novosibirsk, Russia. The DTNS may be described as a line source of neutrons, in contrast to a spallation or a D-Lithium source with neutrons beaming from a point, or a tokamak volume source. The DTNS is a neutral beam driven linear plasma system with magnetic mirrors to confine the energetic deuterium and tritium beam injected ions, which produce the 14 MeV neutrons. The hot ions are imbedded in warm-background plasma, which traps the neutral atoms and provides both MHD and micro stability to the plasma. The 14 MeV neutron flux ranges typically at the level of 1 to 4 MW/m2.

Molvik, A W; Simonen, T C

2009-07-17T23:59:59.000Z

314

Qualification issues associated with the use of advanced instrumentation and control systems hardware in nuclear power plants  

SciTech Connect (OSTI)

The instrumentation and control (I&C) systems in advanced reactors will make extensive use of digital controls, microprocessors, multiplexing, and Tiber-optic transmission. Elements of these advances in I&C have been implemented on some current operating plants. However, the widespread use of the above technologies, as well as the use of artificial intelligence with minimum reliance on human operator control of reactors, highlights the need to develop standards for qualifying I&C used in the next generation of nuclear power plants. As a first step in this direction, the protection system I&C for present-day plants was compared to that proposed for advanced light water reactors (ALWRs). An evaluation template was developed by assembling a configuration of a safety channel instrument string for a generic ALWR, then comparing the impact of environmental stressors on that string to their effect on an equivalent instrument string from an existing light water reactor. The template was then used to address reliability issues for microprocessor-based protection systems. Standards (or lack thereof) for the qualification of microprocessor-based safety I&C systems were also identified. This approach addresses in part issues raised in Nuclear Regulatory Commission policy document SECY-91-292. which recognizes that advanced I&C systems for the nuclear industry are ``being developed without consensus standards, as the technology available for design is ahead of the technology that is well understood through experience and supported by application standards.``

Korsah, K. [Oak Ridge National Lab., TN (United States); Antonescu, C. [Nuclear Regulatory Commission, Rockville, MD (United States). Office of Nuclear Regulatory Research

1993-10-01T23:59:59.000Z

315

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

SciTech Connect (OSTI)

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.

Subudhi, M. [Brookhaven National Lab., Upton, NY (United States)

1996-04-01T23:59:59.000Z

316

Final sludge rules consolidate options  

SciTech Connect (OSTI)

Final federal regulations for use and disposal of waste water sludge were signed in 1992. Now states must adopt standards that are at least as stringent to maintain sludge disposal permitting authority. The regulations define specific limits for 12 sludge contaminants while the organic contaminants listed have been eliminated. The regulations recognize three basic methods of sludge use and disposal: land application, surface disposal, and incineration.

Walsh, T.K. [Metcalf & Eddy Inc., Wakefield, MA (United States)

1993-02-01T23:59:59.000Z

317

FORTE spacecraft vibration mitigation. Final report  

SciTech Connect (OSTI)

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.

Maly, J.R.

1996-02-01T23:59:59.000Z

318

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

SciTech Connect (OSTI)

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

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

2010-10-01T23:59:59.000Z

319

Irradiation of the First Advanced Gas Reactor Fuel Development and Qualification Experiment in the Advanced Test Reactor  

SciTech Connect (OSTI)

The United States Department of Energy’s Advanced Gas Reactor (AGR) Fuel Development and Qualification Program will be irradiating eight separate tri-isotopic (TRISO) particle fuel (in compact form) experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). These irradiations and fuel development are being accomplished to support development of the next generation reactors in the United States. The ATR has a long history of irradiation testing in support of reactor development and the INL has been designated as the United States Department of Energy’s lead laboratory for nuclear energy development. These AGR fuel experiments will be irradiated over the next ten years to demonstrate and qualify new particle fuel for use in high temperature gas reactors. The experiments, which will each consist of six separate capsules, will be irradiated in an inert sweep gas atmosphere with individual on-line temperature monitoring and control for each capsule. The swept gas will also have on-line fission product monitoring to track performance of the fuel in each individual capsule during irradiation. The design of the first experiment (designated AGR-1) was completed in 2005, and the fabrication and assembly of the test train as well as the support systems and fission product monitoring system that monitor and control the experiment during irradiation were completed in September 2006. The experiment was inserted in the ATR in December 2006, and is serving as a shakedown test of the multi-capsule experiment design that will be used in the subsequent irradiations as well as a test of the early variants of the fuel produced under this program. The experiment test train as well as the monitoring, control, and data collection systems are discussed and the status of the experiment is provided.

S. Blaine Grover; David A. Petti

2008-10-01T23:59:59.000Z

320

Completing the Design of the Advanced Gas Reactor Fuel Development and Qualification Experiments for Irradiation in the Advanced Test Reactor  

SciTech Connect (OSTI)

The United States Department of Energy’s Advanced Gas Reactor (AGR) Fuel Development and Qualification Program will be irradiating eight separate low enriched uranium (LEU) oxycarbide (UCO) tri-isotopic (TRISO) particle fuel (in compact form) experiments in the Advanced Test Reactor (ATR) located at the newly formed Idaho National Laboratory (INL). These irradiations and fuel development are being accomplished to support development of the next generation reactors in the United States. The ATR has a long history of irradiation testing in support of reactor development and the INL has been designated as the new United States Department of Energy’s lead laboratory for nuclear energy development. The ATR is one of the world’s premiere test reactors for performing long term, high flux, and/or large volume irradiation test programs. These AGR fuel experiments will be irradiated over the next ten years to demonstrate and qualify new particle fuel for use in high temperature gas reactors. The goals of the irradiation experiments are to provide irradiation performance data to support fuel process development, to qualify fuel for normal operating conditions, to support development and validation of fuel performance and fission product transport models and codes, and to provide irradiated fuel and materials for post irradiation examination (PIE) and safety testing. The experiments, which will each consist of six separate capsules, will be irradiated in an inert sweep gas atmosphere with individual on-line temperature monitoring and control for each capsule. The swept gas will also have on-line fission product monitoring to track performance of the fuel in each individual capsule during irradiation.

S. Blaine Grover

2006-10-01T23:59:59.000Z

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321

New Approaches to Final Cooling  

E-Print Network [OSTI]

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

Neuffer, David

2015-01-01T23:59:59.000Z

322

Field practice internship final report  

SciTech Connect (OSTI)

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.

Foster, T.

1994-05-01T23:59:59.000Z

323

Final_Testimony(2).pdf  

Office of Environmental Management (EM)

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324

Final Green Zia Award Release  

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

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325

Final Meeting Summary Page 1  

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326

Final Meeting Summary Page 1  

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327

Final Meeting Summary Page 1  

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328

Final Meeting Summary Page 1  

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329

Final Meeting Summary Page 1  

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330

Final Meeting Summary Page 1  

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331

Final Meeting Summary Page 1  

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332

Final Meeting Summary Page 1  

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

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333

Final Meeting Summary Page 1  

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334

Final Meeting Summary Page 1  

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

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335

Final Meeting Summary Page 1  

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

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336

Final Meeting Summary Page 1  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicyFeasibilityField Office ProgramsFinal ExamDecember 11,August

337

Final Meeting Summary Page 1  

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

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338

Final Meeting Summary Page 1  

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

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339

Final Meeting Summary Page 1  

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

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340

Final Meeting Summary Page 1  

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

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Note: This page contains sample records for the topic "qualification final" from the National Library of EnergyBeta (NLEBeta).
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341

Final Meeting Summary Page 1  

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

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342

Final Meeting Summary Page 1  

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

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343

Final Meeting Summary Page 1  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicyFeasibilityField Office ProgramsFinal7, 2014 FINALMarch 6, 20138,

344

Final Meeting Summary Page 1  

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

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345

Final Meeting Summary Page 1  

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

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346

Final Meeting Summary Page 1  

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

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347

Final Meeting Summary Page 1  

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

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348

Final Meeting Summary Page 1  

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

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349

Final Meeting Summary Page 1  

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

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350

Final Meeting Summary Page 1  

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

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351

Final Meeting Summary Page 1  

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

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352

Final Meeting Summary Page 1  

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

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353

Final Meeting Summary Page 1  

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

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354

Final Meeting Summary Page 1  

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

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355

Final Meeting Summary Page 1  

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

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356

FinalProgramReportfinal.doc  

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

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357

FINAL TECHNICAL REPORT-DJ  

Office of Scientific and Technical Information (OSTI)

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358

Massively Deployed Sensors Final Project Report  

E-Print Network [OSTI]

Massively Deployed Sensors Final Project Report Power Systems Engineering Research Center Systems Engineering Research Center Massively Deployed Sensors Final Project Report Editors Jonathan project titled "Massively Deployed Sensors," PSERC project T-31. We express our appreciation

359

EIS-0203: Programmatic Final Environmental Impact Statement ...  

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

Impact Statement EIS-0203: Programmatic Final Environmental Impact Statement Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental...

360

PROCEDURES and INSTRUCTIONS for SUBMITTING FINAL ...  

E-Print Network [OSTI]

Apr 16, 2010 ... PROCEDURES and INSTRUCTIONS for SUBMITTING FINAL GRADES. Please view rather than print this information. A version without ...

saerens

2010-04-16T23:59:59.000Z

Note: This page contains sample records for the topic "qualification final" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

Final Environmental Impact Statement August 2013  

E-Print Network [OSTI]

Final Environmental Impact Statement August 2013 Prepared for: State University Construction Fund Conservation Law. A 9 Draft or 9 Final (check one) Environmental Impact Statement has been completed Notice of Completion of Draft / Final EIS Page 2 of 2 Potential Environmental Impacts: A copy

Oh, Kwang W.

362

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

SciTech Connect (OSTI)

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

Vidal, J. F.; Noguere, G.; Peneliau, Y.; Santamarina, A. [CEA, DEN, DER/SPRC/LEPh, Cadarache, F-13108 Saint-Paul-lez-Durance (France)

2012-07-01T23:59:59.000Z

363

IRIS Final Technical Progress Report  

SciTech Connect (OSTI)

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

M. D. Carelli

2003-11-03T23:59:59.000Z

364

Advanced Design Studies. Final report  

SciTech Connect (OSTI)

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

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

2012-12-01T23:59:59.000Z

365

FINAL SCIENTIFIC/TECHNICAL REPORT  

SciTech Connect (OSTI)

Dynalene Inc has developed and patented a fuel cell coolant with the help of DOE SBIR Phase I and Phase II funding (Project DE-FG02-04ER83884). However, this coolant could only be produced in lab scale (500 ml to 2 L) due to problems in the optimization and scale-up of a nanoparticle ingredient. This project optimized the nanoparticle production process in 10 L and 100 L reactors (which translates to about 5000 gallons of coolant), optimized the filtration process for the nanoparticles, and develop a high throughput production as well as quality control method for the final coolant formulation. Scale-up of nanoparticle synthesis (using emulsion polymerization) is an extremely challenging task. Dynalene researchers, in collaboration with a university partner, identified all the parameters affecting the size, charge density and coagulation characteristics of the nanoparticles and then optimized these parameters to achieve the goals and the objectives of this project. Nanoparticle synthesis was demonstrated to be reproducible in the 10 L and 100 L scales.

Satish Mohapatra

2011-12-21T23:59:59.000Z

366

Demand Side Bidding. Final Report  

SciTech Connect (OSTI)

This document sets forth the final report for a financial assistance award for the National Association of Regulatory Utility Commissioners (NARUC) to enhance coordination between the building operators and power system operators in terms of demand-side responses to Location Based Marginal Pricing (LBMP). Potential benefits of this project include improved power system reliability, enhanced environmental quality, mitigation of high locational prices within congested areas, and the reduction of market barriers for demand-side market participants. NARUC, led by its Committee on Energy Resources and the Environment (ERE), actively works to promote the development and use of energy efficiency and clean distributive energy policies within the framework of a dynamic regulatory environment. Electric industry restructuring, energy shortages in California, and energy market transformation intensifies the need for reliable information and strategies regarding electric reliability policy and practice. NARUC promotes clean distributive generation and increased energy efficiency in the context of the energy sector restructuring process. NARUC, through ERE's Subcommittee on Energy Efficiency, strives to improve energy efficiency by creating working markets. Market transformation seeks opportunities where small amounts of investment can create sustainable markets for more efficient products, services, and design practices.

Spahn, Andrew

2003-12-31T23:59:59.000Z

367

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

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

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

368

EIS-0458: EPA Notice of Availability of Final Environmental Impact...  

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

EPA Notice of Availability of Final Environmental Impact Statement EIS-0458: EPA Notice of Availability of Final Environmental Impact Statement EIS-0458: Final EPAEIS No....

369

EIS-0470: Cape Wind Energy Project, Final General Conformity...  

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

70: Cape Wind Energy Project, Final General Conformity Determination EIS-0470: Cape Wind Energy Project, Final General Conformity Determination Cape Wind Energy Project, Final...

370

ITOUGH2 Software Qualification  

E-Print Network [OSTI]

of the mechanism by which refinery Se enters the food web isIt is also not clear how refinery effluent Se, released asThe analysis of a Shell Refinery effluent sample reported in

Fraser, P.

2010-01-01T23:59:59.000Z

371

ITOUGH2 Software Qualification  

E-Print Network [OSTI]

hydride generation atomic absorption spectrometry with on-B y conventional flame atomic absorption (FLAA) methods,hydride generation atomic absorption spectrometry with on-

Fraser, P.

2010-01-01T23:59:59.000Z

372

Chemical Processing Qualification Standard  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-Up fromDepartmentTieCelebrate Earth DayFuels Chemical Kinetic Modeling of16-2010 February

373

Mechanical Systems Qualification Standard  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustion | Department of EnergyDevelopmentTechnologies | Department ofMeasuring the61-2008 June

374

Qualification of Alternative Fuels  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:Year in3.pdfEnergyDepartment ofOil'sofAppendix B,ProtocolPutting ItDepartment

375

Oklahoma seismic network. Final report  

SciTech Connect (OSTI)

The US Nuclear Regulatory Commission has established rigorous guidelines that must be adhered to before a permit to construct a nuclear-power plant is granted to an applicant. Local as well as regional seismicity and structural relationships play an integral role in the final design criteria for nuclear power plants. The existing historical record of seismicity is inadequate in a number of areas of the Midcontinent region because of the lack of instrumentation and (or) the sensitivity of the instruments deployed to monitor earthquake events. The Nemaha Uplift/Midcontinent Geophysical Anomaly is one of five principal areas east of the Rocky Mountain front that has a moderately high seismic-risk classification. The Nemaha uplift, which is common to the states of Oklahoma, Kansas, and Nebraska, is approximately 415 miles long and 12-14 miles wide. The Midcontinent Geophysical Anomaly extends southward from Minnesota across Iowa and the southeastern corner of Nebraska and probably terminates in central Kansas. A number of moderate-sized earthquakes--magnitude 5 or greater--have occurred along or west of the Nemaha uplift. The Oklahoma Geological Survey, in cooperation with the geological surveys of Kansas, Nebraska, and Iowa, conducted a 5-year investigation of the seismicity and tectonic relationships of the Nemaha uplift and associated geologic features in the Midcontinent. This investigation was intended to provide data to be used to design nuclear-power plants. However, the information is also being used to design better large-scale structures, such as dams and high-use buildings, and to provide the necessary data to evaluate earthquake-insurance rates in the Midcontinent.

Luza, K.V.; Lawson, J.E. Jr. [Oklahoma Geological Survey, Norman, OK (United States)]|[Univ. of Oklahoma, Norman, OK (United States). Energy Center

1993-07-01T23:59:59.000Z

376

Thermal blooming experiments. Final report  

SciTech Connect (OSTI)

The goals of this program were to design an experiment for determining the effect of stimulated thermal Brillouin scattering (STBS) on single pulse laser propagation and to establish the ability of both a wave optics code and of linearized theory to predict the results of the experiment accurately. The second goal is particularly important because no experimental verification of analytical tools currently in use for single pulse high power laser propagation is available. When a high power laser propagates through the atmosphere, a small fraction of the laser energy is absorbed, creating acoustic waves that may move a significant distance transverse to the propagation direction during the pulse. Such waves lead to the well-known t{sup 3}-blooming refractive-index variations. When such blooming is sufficiently strong, the induced refractive-index alters the intensity profile of the beam farther along the propagation path. This altered intensity profile induces a somewhat different refractive-index profile that may reinforce the path-integrated t{sup 3} blooming. This self-enhancement may be called near-forward stimulated thermal Brillouin scattering (STBS). The design effort described here was carried out much like the proposed experimental program, which calls for the interaction of experimental work with analytical theory and with a wave optics code, A linearized theory of STBS was developed. Results from this theory were compared to output from a wave optics propagation code for several well defined sets of operating conditions. Once good agreement between theory and code simulation was obtained for these test conditions, the theory was used to define and operating regime for a laboratory scale thermal blooming experiment that would provide information relevant to high power laser propagation. A conceptual design for this experiment was then generated and, finally, and experimental set-up, including diagnostics, was proposed.

Not Available

1990-05-01T23:59:59.000Z

377

Energy Department Finalizes Loan Guarantee for Transformational...  

Office of Environmental Management (EM)

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

378

Geothermal: Sponsored by OSTI -- Final Report  

Office of Scientific and Technical Information (OSTI)

Final Report Geothermal Technologies Legacy Collection HelpFAQ | Site Map | Contact Us | Admin Log On HomeBasic Search About Publications Advanced Search New Hot Docs News...

379

Final Conservation Billing Credit Policy Supplement Background...  

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

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

380

Final Report - Hydrogen Delivery Infrastructure Options Analysis...  

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

- Hydrogen Delivery Infrastructure Options Analysis Final Report - Hydrogen Delivery Infrastructure Options Analysis This report, by the Nexant team, documents an in-depth analysis...

Note: This page contains sample records for the topic "qualification final" from the National Library of EnergyBeta (NLEBeta).
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381

Final Report Port and Modal Elasticity Study  

E-Print Network [OSTI]

1 Final Report Port and Modal Elasticity Study Prepared for Southern California Association................................................................................................. 23 Financing Transportation Infrastructure for Port Access ..................................................................................... 27 Comparison of West Coast Port Facilities

California at Berkeley, University of

382

Hadronic Final States and QCD: Summary  

SciTech Connect (OSTI)

A summary of new experimental results and recent theoretical developments discussed in the 'Hadronic Final States and QCD' working group is presented.

Gehrmann, Thomas; /Zurich U.; Grindhammer, Guenter; /Munich, Max Planck Inst.; O'Dell, Vivian; /Fermilab; Walczak, Roman; /Oxford U.

2008-08-01T23:59:59.000Z

383

AGR-1 Irradiation Test Final As-Run Report  

SciTech Connect (OSTI)

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

Blaise P. Collin

2012-06-01T23:59:59.000Z

384

AGR-2 IRRADIATION TEST FINAL AS-RUN REPORT  

SciTech Connect (OSTI)

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

Blaise, Collin

2014-07-01T23:59:59.000Z

385

Standard practice for qualification and acceptance of boron based metallic neutron absorbers for nuclear criticality control for dry cask storage systems and transportation packaging  

E-Print Network [OSTI]

1.1 This practice provides procedures for qualification and acceptance of neutron absorber materials used to provide criticality control by absorbing thermal neutrons in systems designed for nuclear fuel storage, transportation, or both. 1.2 This practice is limited to neutron absorber materials consisting of metal alloys, metal matrix composites (MMCs), and cermets, clad or unclad, containing the neutron absorber boron-10 (10B). 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

American Society for Testing and Materials. Philadelphia

2007-01-01T23:59:59.000Z

386

Final Report Package_Winnebago  

SciTech Connect (OSTI)

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

Carolyn Stewart, Director, Red Mountain Energy Partners

2006-10-31T23:59:59.000Z

387

Santa Barbara Final Technical Report  

SciTech Connect (OSTI)

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

Hacker, Angela; Hansen, Sherman; Watkins, Ashley

2013-11-30T23:59:59.000Z

388

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

SciTech Connect (OSTI)

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

Shafer, A.

2010-05-05T23:59:59.000Z

389

FINAL STAFF FORECAST OF 2008 PEAK DEMAND  

E-Print Network [OSTI]

CALIFORNIA ENERGY COMMISSION FINAL STAFF FORECAST OF 2008 PEAK DEMAND STAFFREPORT June 2007 CEC-200 of the information in this paper. #12;Abstract This document describes staff's final forecast of 2008 peak demand demand forecasts for the respective territories of the state's three investor-owned utilities (IOUs

390

Sustainability Initiative Task Force Final Report  

E-Print Network [OSTI]

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

Sheridan, Jennifer

391

EA-1836: Final Environmental Assessment | Department of Energy  

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

Final Environmental Assessment EA-1836: Final Environmental Assessment Norwich Cogeneration Initiative, Norwich, Connecticut The DOE National Energy Technology Laboratory (NETL)...

392

EIS-0236-S4: Final Supplemental Programmatic Environmental Impact...  

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

Final Supplemental Programmatic Environmental Impact Statement EIS-0236-S4: Final Supplemental Programmatic Environmental Impact Statement Complex Transformation The National...

393

Microsoft Word - Agencies Publish Final Environmental Impact...  

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

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

394

FINAL STAFF REPORT FORMS AND INSTRUCTIONS FOR  

E-Print Network [OSTI]

FINAL STAFF REPORT FORMS AND INSTRUCTIONS FOR ELECTRICITY DEMAND FORECASTS Prepared in Support. The information relates to electricity demand forecasts, demand-side management and energy efficiency impacts-2012. Keywords: Electricity demand, consumption, forecast, peak, self-generation, conservation, demand

395

CALIFORNIA ENERGY DEMAND 20122022 FINAL FORECAST  

E-Print Network [OSTI]

CALIFORNIA ENERGY DEMAND 20122022 FINAL FORECAST Volume 2: Electricity Demand.Oglesby Executive Director #12;i ACKNOWLEDGEMENTS The demand forecast is the combined product estimates. Margaret Sheridan provided the residential forecast. Mitch Tian prepared the peak demand

396

COMMITTEE FINAL REPORT REVISED SHORTTERM PEAK  

E-Print Network [OSTI]

COMMITTEE FINAL REPORT REVISED SHORTTERM PEAK DEMAND FORECAST (20112012) MARCH 2011 CEC. #12; i ABSTRACT This report presents revised shortterm peak demand forecasts for the California, and San Diego Gas & Electric transmission access charge areas. Keywords: Forecast, peak demand

397

MEASUREMENTS TAKEN IN SUPPORT OF QUALIFICATION OF PROCESSING SAVANNAH RIVER SITE LOW-LEVEL LIQUID WASTE INTO SALTSTONE  

SciTech Connect (OSTI)

The Saltstone Facility at the Savannah River Site (SRS) immobilizes low-level liquid waste into Saltstone to be disposed of in the Z-Area Saltstone Disposal Facility, Class Three Landfill. In order to meet the permit conditions and regulatory limits set by the South Carolina Department of Health and Environmental Control (SCDHEC), the Resource Conservation and Recovery Act (RCRA) and the Environmental Protection Agency (EPA), both the low-level salt solution and Saltstone samples are analyzed quarterly. Waste acceptance criteria (WAC) are designed to confirm the salt solution sample from the Tank Farm meets specific radioactive and chemical limits. The toxic characteristic leaching procedure (TCLP) is used to confirm that the treatment has immobilized the hazardous constituents of the salt solution. This paper discusses the methods used to characterize the salt solution and final Saltstone samples from 2007-2009.

Reigel, M.; Bibler, N.; Diprete, C.; Cozzi, A.; Staub, A.; Ray, J.

2010-01-27T23:59:59.000Z

398

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

SciTech Connect (OSTI)

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

Binh T. Pham; Jeffrey J. Einerson

2013-09-01T23:59:59.000Z

399

2006 Long Range Development Plan Final Environmental Impact Report  

E-Print Network [OSTI]

Vol: Reduced Vol: 112 399 PCE Adj: MLF Adj: Final Vol. :Vol: Reduced Vol: 186 203 PCE Adj: MLF Adj: Final Vol. :Reduct Vol: Reduced Vol: 137 PCE Adj: MLF Adj: Final Vol. :

Philliber, Jeff

2007-01-01T23:59:59.000Z

400

apprenticeship program final: Topics by E-print Network  

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

to and screened Jun, Suckjoon 15 Stanford Geothermal Program Final Report Renewable Energy Websites Summary: Linear Programming1 Stanford Geothermal Program Final Report July...

Note: This page contains sample records for the topic "qualification final" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

EA-1183: Final Environmental Assessment | Department of Energy  

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

183: Final Environmental Assessment EA-1183: Final Environmental Assessment Coal-fired Diesel Generator University of Alaska, Fairbanks, Alaska This EA evaluates the environmental...

402

EA-1603: Final Environmental Assessment | Department of Energy  

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

03: Final Environmental Assessment EA-1603: Final Environmental Assessment Expansion of Permitted Land and Operations at the 9940 Complex and Thunder Range at Sandia National...

403

EA-1146: Final Environmental Assessment | Department of Energy  

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

46: Final Environmental Assessment EA-1146: Final Environmental Assessment Radioactive Waste Storage at Rocky Flats Environmental Technology Site, Golden, Colorado This EA...

404

EA-1170: Final Environmental Assessment | Department of Energy  

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

70: Final Environmental Assessment EA-1170: Final Environmental Assessment Area 5 Radioactive Waste Management Site Access Improvement at the Nevada Test Site The Department of...

405

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

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

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

406

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

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

EPA Notice of Availability of the Final Environmental Impact Statement Cushman Hydroelectric Project (FERC No. 0456) Notice of Availability for the Final Environmental Impact...

407

EA-0073: Final Environmental Assessment | Department of Energy  

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

EA-0073: Final Environmental Assessment EA-0073: Final Environmental Assessment Yucca Mountain Site, Nevada Research and Development Area, Nevada The Nuclear Waste Policy Act of...

408

DOE Issues Test Procedure Final Rule & Publishes Energy Conservation...  

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

Test Procedure Final Rule & Publishes Energy Conservation Standards NOPR for Electric Motors DOE Issues Test Procedure Final Rule & Publishes Energy Conservation Standards NOPR for...

409

Final Environmental Assessment of the National Renewable Energy...  

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

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

410

Energy Department Finalizes $646 Million Loan Guarantee to Support...  

Energy Savers [EERE]

Energy Department Finalizes 646 Million Loan Guarantee to Support Innovative Solar Power Plant Energy Department Finalizes 646 Million Loan Guarantee to Support Innovative Solar...

411

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

Office of Environmental Management (EM)

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

412

assessment program final: Topics by E-print Network  

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

25 Next Page Last Page Topic Index 1 Stanford Geothermal Program Final Report Renewable Energy Websites Summary: Linear Programming1 Stanford Geothermal Program Final Report July...

413

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

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

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

414

LM Issues Final Programmatic Environmental Impact Statement on...  

Office of Environmental Management (EM)

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

415

EIS-0259: Final Environmental Impact Statement | Department of...  

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

9: Final Environmental Impact Statement EIS-0259: Final Environmental Impact Statement Disposal of Decommissioned, Defueled Cruiser, Ohio Class, Los Angeles and Class Naval Reactor...

416

Agencies Publish Final Environmental Impact Statement on Energy...  

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

Final Environmental Impact Statement on Energy Corridor Designation in the West Agencies Publish Final Environmental Impact Statement on Energy Corridor Designation in the West...

417

EIS-0294: Final Environmental Impact Statement | Department of...  

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

Final Environmental Impact Statement EIS-0294: Final Environmental Impact Statement Sutter Power Project Western Area Power Administration operates and maintains a high-voltage...

418

EIS-0493: FERC Notice of Availability of Final Environmental...  

Office of Environmental Management (EM)

493: FERC Notice of Availability of Final Environmental Impact Statement EIS-0493: FERC Notice of Availability of Final Environmental Impact Statement Corpus Christi LNG Terminal...

419

EIS-0386: EPA Notice of Availability of the Programmatic Final...  

Office of Environmental Management (EM)

EIS-0386: EPA Notice of Availability of the Programmatic Final Environmental Impact Statement EIS-0386: EPA Notice of Availability of the Programmatic Final Environmental Impact...

420

Final Supplemental Environmental Impact Statement for a Geologic...  

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

- Nevada Rail Transportation Corridor DOEEIS-0250F-S2 and Final Env Final Supplemental Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear...

Note: This page contains sample records for the topic "qualification final" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

EIS-0212: Final Environmental Impact Statement | Department of...  

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

EIS-0212: Final Environmental Impact Statement EIS-0212: Final Environmental Impact Statement Safe Interim Storage of Hanford Tank Wastes, Hanford Site, Richland, Washington This...

422

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

Open Energy Info (EERE)

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

423

EIS-0256: Final Environmental Impact Statement | Department of...  

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

6: Final Environmental Impact Statement EIS-0256: Final Environmental Impact Statement Sierra Pacific Power Company Alturas Transmission Line Project This Environmental Impact...

424

DOE Issues Final Site-Wide Environmental Impact Statement for...  

Office of Environmental Management (EM)

DOE Issues Final Site-Wide Environmental Impact Statement for the Nevada National Security Site DOE Issues Final Site-Wide Environmental Impact Statement for the Nevada National...

425

EA-1801: Final Environmental Impact | Department of Energy  

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

Final Environmental Impact EA-1801: Final Environmental Impact Granite Reliable Power Wind Project, Coos County, New Hampshire Granite Reliable Power, LLC, a subsidiary of Noble...

426

EIS-0511: FERC Notice of Availability of FInal Environmental...  

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

511: FERC Notice of Availability of FInal Environmental Impact Statement EIS-0511: FERC Notice of Availability of FInal Environmental Impact Statement Aguirre Offshore GasPort...

427

EIS-0444: EPA Notice of Availability of the Final Environmental...  

Office of Environmental Management (EM)

Final Environmental Impact Statement EIS-0444: EPA Notice of Availability of the Final Environmental Impact Statement Texas Clean Energy Project, Ector, Texas 2011-19917.pdf More...

428

Finalize Historic National Program to Reduce Greenhouse Gases...  

Open Energy Info (EERE)

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

429

EA-1247: Final Environmental Assessment | Department of Energy  

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

247: Final Environmental Assessment EA-1247: Final Environmental Assessment Electrical Power System Upgrades at Los Alamos National Laboratory This EA evaluates the environmental...

430

EA-1097: Final Environmental Assessment | Department of Energy  

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

097: Final Environmental Assessment EA-1097: Final Environmental Assessment Solid waste Disposal - Nevada Test Site, Nye County, Nevada This EA evaluates the environmental impacts...

431

EA-1092: Final Environmental Assessment | Department of Energy  

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

activities. EA-1092-FEA-1995.pdf More Documents & Publications EA-1001: Final Environmental Assessment EA-1053: Final Environmental Assessment EIS-0026: Mitigation Action Plan...

432

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

Office of Environmental Management (EM)

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

433

EA-1190: Final Environmental Assessment | Department of Energy  

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

0: Final Environmental Assessment EA-1190: Final Environmental Assessment Wastewater Treatment Capability Upgrade This EA evaluates the environmental impacts for the proposed...

434

EA-1635: Final Environmental Assessment | Department of Energy  

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

35: Final Environmental Assessment EA-1635: Final Environmental Assessment Williston to Tioga Transmission Line Project Pre-Approval Review Basin Electric Power Cooperative (BEPC)...

435

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

Office of Environmental Management (EM)

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

436

EIS-0244: Final Environmental Impact Statement | Department of...  

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

EIS-0244: Final Environmental Impact Statement EIS-0244: Final Environmental Impact Statement Plutonium Finishing Plant Stabilization This EIS evaluates the impacts on the human...

437

EIS-0460: EPA Notice of Availability of Final Environmental Impact...  

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

EPA Notice of Availability of Final Environmental Impact Statement EIS-0460: EPA Notice of Availability of Final Environmental Impact Statement FutureGen 2.0 Project, Morgan...

438

EIS-0418: EPA Notice of Availability of the Final Environmental...  

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

EPA Notice of Availability of the Final Environmental Impact Statement EIS-0418: EPA Notice of Availability of the Final Environmental Impact Statement South Dakota PrairieWinds...

439

EIS-0240: Final Environmental Impact Statement | Department of...  

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

40: Final Environmental Impact Statement EIS-0240: Final Environmental Impact Statement Disposition of Surplus Highly Enriched Uranium This document assesses the environmental...

440

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

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

EPA Notice of Availability of Final Environmental Impact Statement EIS-0400: EPA Notice of Availability of Final Environmental Impact Statement Granby Pumping Plant...

Note: This page contains sample records for the topic "qualification final" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


441

EIS-0377: DOE Notice of Availability of the Final Environmental...  

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

Final Environmental Impact Statement EIS-0377: DOE Notice of Availability of the Final Environmental Impact Statement Big Stone II Power Plant and Transmission Project The Western...

442

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

Office of Environmental Management (EM)

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

443

EIS-0336: EPA Notice of Availability of the Final Environmental...  

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

6: EPA Notice of Availability of the Final Environmental Impact Statement EIS-0336: EPA Notice of Availability of the Final Environmental Impact Statement Tucson Electric Power...

444

EIS-0425: EPA Notice of Availability of a Final Environmental...  

Office of Environmental Management (EM)

25: EPA Notice of Availability of a Final Environmental Impact Statement EIS-0425: EPA Notice of Availability of a Final Environmental Impact Statement Bonneville Power...

445

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

Energy Savers [EERE]

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

446

EIS-0361: EPA Notice of Availability of the Final Environmental...  

Office of Environmental Management (EM)

361: EPA Notice of Availability of the Final Environmental Impact Statement EIS-0361: EPA Notice of Availability of the Final Environmental Impact Statement Western Greenbrier...

447

EIS-0423: EPA Notice of Availability of the Final Environmental...  

Office of Environmental Management (EM)

EPA Notice of Availability of the Final Environmental Impact Statement EIS-0423: EPA Notice of Availability of the Final Environmental Impact Statement Long -Term Management and...

448

EIS-0197: Final Environmental Impact Statement | Department of...  

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

97: Final Environmental Impact Statement EIS-0197: Final Environmental Impact Statement Delivery of the Canadian Entitlement This EIS is being prepared to aid the decision the...

449

EIS-0427: EPA Notice of Availability of a Final Environmental...  

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

EPA Notice of Availability of a Final Environmental Impact Statement EIS-0427: EPA Notice of Availability of a Final Environmental Impact Statement Interconnection of the Grapevine...

450

Energy Department Finalizes $737 Million Loan Guarantee to Tonopah...  

Office of Environmental Management (EM)

Finalizes 737 Million Loan Guarantee to Tonopah Solar Energy for Nevada Project Energy Department Finalizes 737 Million Loan Guarantee to Tonopah Solar Energy for Nevada Project...

451

EA-1698: Final Environmental Assessment | Department of Energy  

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

Final Environmental Assessment EA-1698: Final Environmental Assessment Baldwin Wind Energy Center The Baldwin Wind Energy Center (Project or Proposed Action) is a wind generation...

452

EA-1465: Final Environmental Assessment | Department of Energy  

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

65: Final Environmental Assessment EA-1465: Final Environmental Assessment Wind Energy Center EdgeleyKulm Project, North Dakota The proposed EdgeleyKulm Project is a 21-megawatt...

453

EA-0965: Final Environmental Assessment | Department of Energy  

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

0965: Final Environmental Assessment EA-0965: Final Environmental Assessment Cancer Research Center Indiana University School of Medicine This EA evaluates the environmental...

454

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

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

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

455

EA-1832: Final Environmental Assessment | Department of Energy  

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

Final Environmental Assessment EA-1832: Final Environmental Assessment Rainier Biogas LLC Community Anaerobic Manure Digester, Enumclaw, Washington This project is located...

456

EA-1797: Final Environmental Assessment | Department of Energy  

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

Final Environmental Assessment EA-1797: Final Environmental Assessment Loan Guarantee for the Agua Caliente Solar Project in Yuma County, Arizona The U.S. Department of Energy...

457

EIS-0485: EPA Notice of Availability of Final Environmental Impact...  

Office of Environmental Management (EM)

of Final Environmental Impact Statement Interconnection of the Grande Prairie Wind Farm, Holt County, Nebraska EPA announced the availability of a Final EIS that...

458

EA-1178: Final Environmental Assessment | Department of Energy  

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

178: Final Environmental Assessment EA-1178: Final Environmental Assessment 300 Area Steam Plant Replacement, Hanford Site, Richland, Washington This EA evaluates the environmental...

459

Building America Expert Meeting Final Report: Multifamily Hydronic...  

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

Meeting Final Report: Multifamily Hydronic and Steam Heating Controls and Distribution Retrofits Building America Expert Meeting Final Report: Multifamily Hydronic and Steam...

460

EA-1692: Final Environmental Assessment | Department of Energy  

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

Final Environmental Assessment EA-1692: Final Environmental Assessment Construction and Start-Up of an Activated Carbon Manufacturing Facility in Red River Parish, Louisiana The...

Note: This page contains sample records for the topic "qualification final" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


461

Project Final Report UBC LBS Project Services1 Project Final Report UBC LBS Project Services2  

E-Print Network [OSTI]

Project Final Report UBC LBS Project Services1 #12;Project Final Report UBC LBS Project Services2 EXECUTIVE SUMMARY The purpose of the UBC Project Services web-based project management portal project on campus within Project Services, and with the rest of the UBC community. We began this project by defining

462

Intelligent wind power prediction systems final report  

E-Print Network [OSTI]

Intelligent wind power prediction systems ­ final report ­ Henrik Aalborg Nielsen (han (FU 4101) Ens. journal number: 79029-0001 Project title: Intelligent wind power prediction systems #12;#12;Intelligent wind power prediction systems 1/36 Contents 1 Introduction 6 2 The Wind Power Prediction Tool 7 3

463

FINAL REPORT ARIZONA WATER INSTITUTE PROJECT  

E-Print Network [OSTI]

1-17-08 FINAL REPORT ARIZONA WATER INSTITUTE PROJECT "ARIZONA TRIBAL APPROACHES TO WATER of Arizona. The project, "Arizona Tribal Approaches to Water Management," focused OIl developing research and analysis to support tribal water resources management. The project workplan included development of a core

Fay, Noah

464

COST 526 Project CH4 Final Report  

E-Print Network [OSTI]

1 COST 526 ­ Project CH4 Final Report Modelling, Simulating and Analysing EQ-Casting and Quenching. Remark: Due to the delay of the funding of the proposed investment casting project we change the focus of the project. The development of an Open Source optimization tool (see collaboration) was a relevant

465

IXTOC OIL SPILL ASSESSMENT FINAL REPORT  

E-Print Network [OSTI]

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

Mathis, Wayne N.

466

I MTI 79TR68 FINAL REPORT  

E-Print Network [OSTI]

#12;I MTI 79TR68 FINAL REPORT A HIGH SEASONAL PERFORMANCE FACTOR GAS HEAT PUMP FOR THE NORTH Demonstration of a High SPF Gas Heat Pump for the North Central United States Table of Contents Appendix Volume evaluation of the market potential for the non- residential heating and cooling market was conducted

Oak Ridge National Laboratory

467

Decommissioning of DR 1 Final report  

E-Print Network [OSTI]

and lessons learned 43 9 Clearance of materials, building and surrounding area 44 9.1 Clearance criteria 44 9Decommissioning of DR 1 Final report DD-18(EN) rev.1 Document approved by the nuclear regulatory authorities Danish Decommissioning, Roskilde January 2006 #12;Author: Kurt Lauridsen Title: Decommissioning

468

Enrollment Analysis Final for Fall 2014  

E-Print Network [OSTI]

) November 6, 2014 Project Request: Enrollment Analysis ­ Final for Fall 2014. Requested by: Dr. Brooks Keel, President; Dr. Teresa Thompson, Vice President, Student Affairs and Enrollment Management Project Abstract, progression, and graduation. Methodology: The following items and their sources are included in this report

Hutcheon, James M.

469

(7 ________final radiation uI  

E-Print Network [OSTI]

at the chamber wall. Fig. 1. Schematic of a laser-IFE power plant beamline. Laser-Induced Damage in Optical simple thermal diffusion scaling from long-pulse results. Keywords: metal mirror, final optic, inertial laser pulses with a fluence of 5 J/cm2 normal to the incident laser beam. We want to simulate an IFE

Harilal, S. S.

470

The Power of Experience Final Report  

E-Print Network [OSTI]

hydrogen economy for providing carbon-free fuels in transportation sector. #12;Hydrogen DeliveryThe Power of Experience Final Report Hydrogen Delivery Infrastructure Options Analysis DOE;Hydrogen Delivery Infrastructure Options Analysis ii TABLE OF CONTENTS SECTION 1 EXECUTIVE SUMMARY

471

MERIT Hg System Final Design Review  

E-Print Network [OSTI]

MERIT Hg System Final Design Review Hg Target System Operations V.B. Graves P.T. Spampinato T Facility Constraints · No overhead lifting capability within tunnel · Modularity required - Component 2 (In- beam) · Baseplate & magnet will go in beam line prior to Hg system · Blocks under magnet end

McDonald, Kirk

472

FINAL DRAFT VI. Application 3: Recruitment Prediction  

E-Print Network [OSTI]

FINAL DRAFT 106 VI. Application 3: Recruitment Prediction Contributors: S. Sarah Hinckley, Bernard Megrey, Thomas Miller Definition What do we mean by recruitment prediction? The first thing to consider in defining this term is the time horizon of the prediction. Short-term predictions mean the use of individual

Miller, Tom

473

CALIFORNIA ENERGY DEMAND 20142024 FINAL FORECAST  

E-Print Network [OSTI]

CALIFORNIA ENERGY DEMAND 2014­2024 FINAL FORECAST Volume 1: Statewide Electricity Demand in this report. #12;i ACKNOWLEDGEMENTS The demand forecast is the combined product of the hard work to the residential forecast. Mitch Tian prepared the peak demand forecast. Ravinderpal Vaid provided the projections

474

CALIFORNIA ENERGY DEMAND 20122022 FINAL FORECAST  

E-Print Network [OSTI]

CALIFORNIA ENERGY DEMAND 20122022 FINAL FORECAST Volume 1: Statewide Electricity forecast is the combined product of the hard work and expertise of numerous staff members in the Demand prepared the peak demand forecast. Ravinderpal Vaid provided the projections of commercial floor space

475

CALIFORNIA ENERGY DEMAND 20142024 FINAL FORECAST  

E-Print Network [OSTI]

CALIFORNIA ENERGY DEMAND 20142024 FINAL FORECAST Volume 2: Electricity Demand The demand forecast is the combined product of the hard work and expertise of numerous California Energy for demand response program impacts and contributed to the residential forecast. Mitch Tian prepared

476

Fusion Policy Advisory Committee FINAL REPORT  

E-Print Network [OSTI]

Fusion Policy Advisory Committee (FPAC) FINAL REPORT September 1990 Report of the Technical Panel on Magnetic Fusion of the Energy Research Advisory Board Washington, D .C. 20585 #12;#12;Fusion Policy of your Fusion Policy Advisory Committee. It presents a fusion policy that the Committee believes

477

Modeling of GE Appliances: Final Presentation  

SciTech Connect (OSTI)

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

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

2013-01-31T23:59:59.000Z

478

Final Technical Report: Hawaii Hydrogen Center for  

E-Print Network [OSTI]

Alkaline Electrolyzer System 8 2.4.1.2 5 kW PEM Fuel Cell System 9 2.4.2 Experiments/Results and Economic 2.8 Acknowledgements 47 2.9 References 47 3 Task 2 ­ Hydrogen Fuel Purity Assessment 49 3.1 GoalsFinal Technical Report: Hawaii Hydrogen Center for Development and Deployment of Distributed Energy

479

Biodiesel Engine Testing MECH-457 Final Report  

E-Print Network [OSTI]

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

480

November 30, 2006 Final Author's Version  

E-Print Network [OSTI]

Electrode Potential in Methanol, Acetonitrile, and Dimethyl Sulfoxide Casey P. Kelly Christopher J. Cramer, acetonitrile, and dimethyl sulfoxide (DMSO) have been determined using a combination of experimental/mol for the absolute solvation free energy of the proton in methanol, acetonitrile, and DMSO, respectively. The final

Truhlar, Donald G

Note: This page contains sample records for the topic "qualification final" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


481

ENGINEERING EDUCATION IN INDIA Draft Final report  

E-Print Network [OSTI]

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

Banerjee, Rangan

482

HANFORD THYROID DISEASE STUDY FINAL REPORT  

E-Print Network [OSTI]

HANFORD THYROID DISEASE STUDY FINAL REPORT Study Management Team Scott Davis, Ph.D., Principal;Acknowledgments Many individuals have contributed to the success of the Hanford Thyroid Disease Study. We wish: Dr. Floyd Frost and Mr. Eugene Sobota; 3) history of Hanford: Dr. Michelle Stenejhem; 4) statistical

483

FINAL REPORT FOR: OPTIMIZATION OF BIOLOGICAL  

E-Print Network [OSTI]

AND SUSPENDED GROWTH WASTEWATER TREATMENT SYSTEM DECEMBER, 1994 Prepared for: Environment Canada Environment#12;FINAL REPORT FOR: OPTIMIZATION OF BIOLOGICAL PHOSPHORUS AND AMMONIA REMOVAL IN A COMBINED FIXED;Optimization of Biological Phosphorus and Ammonia Removal in a Combined Fixed & Suspended Growth System i

484

Final Technical Report - DE-EE0003542  

SciTech Connect (OSTI)

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

Haley, James D

2013-03-31T23:59:59.000Z

485

ENERGIES RENOVABLES NOTES FINALS 2006 COGNOMS, NOM ASSISTNCIA TREBALL NOTA  

E-Print Network [OSTI]

ENERGIES RENOVABLES NOTES FINALS 2006 COGNOMS, NOM ASSISTĂ?NCIA TREBALL NOTA ALCOVERRO VIDAL, MARCEL

Batiste, Oriol

486

UC Davis 2003 LRDP Final Environmental Impact Report Addendum #1  

E-Print Network [OSTI]

UC Davis 2003 LRDP Final Environmental Impact Report Addendum #1 November 2006 Page 1 1 FINAL ADDENDUM #1 TO THE 2003 LONG RANGE DEVELOPMENT PLAN ENVIRONMENTAL IMPACT REPORT (State Clearinghouse No ("University") certified the Final Environmental Impact Report ("Final EIR") (State Clearinghouse Number

California at Davis, University of

487

Final Project Due: May 18, 2010  

E-Print Network [OSTI]

1 Geos 206 Final Project Due: May 18, 2010 Save the trees, and the music stands: An Energy: Monthly totals Total Electricity in kWh Average kWh per day Cost $.11/kWh Emissions .41 kg/kWh (unit in kg electricity bill, cost and emissions of the Bernhard/Chapin complex. 4 Figure 3: This graph provides a monthly

Aalberts, Daniel P.

488

1995 PVUSA progress report. Final report  

SciTech Connect (OSTI)

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

NONE

1996-03-01T23:59:59.000Z

489

Emergency building temperature restrictions. Final evaluation  

SciTech Connect (OSTI)

On July 5, 1979, DOE promulgated final regulations of the Emergency Building Temperature Restrictions program, placing emergency restrictions on thermostat settings for space heating, space cooling, and hot water in commercial, industrial, and nonresidential public buildings. The final regulations restricted space heating to a maximum of 65/sup 0/F, hot water temperature to a maximum of 105/sup 0/F, and cooling temperature to a minimum of 78/sup 0/F. A comprehensive evaluation of the entire EBTF program for a nine-month period from July 16, 1979 is presented. In Chapter 1, an estimate of the population of buildings covered by EBTR is presented. In Chapter 2, EBTR compliance by building type and region is reported. Exemptions are also discussed. In Chapter 3, the simulations of building energy use are explained and the relative impact of various building characteristics and effectiveness of different control strategies are estimated. Finally, in Chapter 4, the methodology for scaling the individual building energy savings to the national level is described, and estimated national energy savings are presented.

None

1980-11-01T23:59:59.000Z

490

ATAC Process Proof of Concept Final Report  

SciTech Connect (OSTI)

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

Bri Rolston; Sarah Freeman

2014-03-01T23:59:59.000Z

491

Cost comparisons of alternative landfill final covers  

SciTech Connect (OSTI)

A large-scale field demonstration comparing and contrasting final landfill cover designs has been constructed and is currently being monitored. Four alternative cover designs and two conventional designs (a RCRA Subtitle ``D`` Soil Cover and a RCRA Subtitle ``C`` Compacted Clay Cover) were constructed of uniform size, side-by-side. The demonstration is intended to evaluate the various cover designs based on their respective water balance performance, ease and reliability of construction, and cost. This paper provides an overview of the construction costs of each cover design.

Dwyer, S.F.

1997-02-01T23:59:59.000Z

492

Final Report: Performance Engineering Research Institute  

SciTech Connect (OSTI)

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

Mellor-Crummey, John [Rice University

2014-10-27T23:59:59.000Z

493

Si concentrator solar cell development. [Final report  

SciTech Connect (OSTI)

This is the final report of a program to develop a commercial, high-efficiency, low-cost concentrator solar cell compatible with Spectrolab`s existing manufacturing infrastructure for space solar cells. The period covered is between 1991 and 1993. The program was funded through Sandia National Laboratories through the DOE concentrator initiative and, was also cost shared by Spectrolab. As a result of this program, Spectrolab implemented solar cells achieving an efficiency of over 19% at 200 to 300X concentration. The cells are compatible with DOE guidelines for a cell price necessary to achieve a cost of electricity of 12 cents a kilowatthour.

Krut, D.D. [Spectrolab, Inc., Sylmar, CA (United States)

1994-10-01T23:59:59.000Z

494

Final Information Quality Bulletin for Peer Review  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAX POLICIES ANDIndustrialEnergyFinal FY 2009 NEUP RD Awards (2).xlsCOVER SHEET04

495

Final TOPS Rpt-10pt.PDF  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAX POLICIES ANDIndustrialEnergyFinal FY 2009 NEUP RDFinal Site-Widefor

496

Final Workshop of Department's Inaugural Technology Assessment |  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAX POLICIES ANDIndustrialEnergyFinal FY 2009 NEUP RDFinalDepartment of Energy

497

Download the Final Agenda | Department of Energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:Year in Review: TopEnergy DOEDealingVehicle1 Guidanceflash2004-12.pdfDownhole Sensor HoldsFinal

498

Final Design RM | Department of Energy  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) " ,"ClickPipelinesProvedDecember 2005DepartmentDecember U.S. Department-5FederalFeds feedFerrinFinal Design

499

Final ECR 2008 Report | Department of Energy  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power SystemsResourcesFLASH2011-11-OPAMFY 2007 TotalFinal Design Review Module March 2010

500

Final Rule Technical Amendment | Department of Energy  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power SystemsResourcesFLASH2011-11-OPAMFY 2007 TotalFinal Design Review ModuleDecember 4,Technical