Sample records for treatment procedure qualification

  1. Heat Treatment Procedure Qualification for Steel Castings

    SciTech Connect (OSTI)

    Professor Robert C. Voigt

    2003-02-02T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Tuohig, W. (Honeywell FM& T, Kansas City, MO); Mahoney, Patrick A.; Tuttle, Bruce Andrew; Wheeler, Jill Susanne

    2009-02-01T23:59:59.000Z

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

  3. Specification and qualification of welding procedures for metallic materials : Welding procedure test : Part 2: Arc welding of aluminium and its alloys

    E-Print Network [OSTI]

    International Organization for Standardization. Geneva

    2005-01-01T23:59:59.000Z

    Specification and qualification of welding procedures for metallic materials : Welding procedure test : Part 2: Arc welding of aluminium and its alloys

  4. Specification and qualification of welding procedures for metallic materials : Welding procedure test : Part 2: Arc welding of aluminium and its alloys : technical corrigendum 1

    E-Print Network [OSTI]

    International Organization for Standardization. Geneva

    2005-01-01T23:59:59.000Z

    Specification and qualification of welding procedures for metallic materials : Welding procedure test : Part 2: Arc welding of aluminium and its alloys : technical corrigendum 1

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

    SciTech Connect (OSTI)

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

    2003-07-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    1994-12-31T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Herman, Connie C.

    2013-09-30T23:59:59.000Z

    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.

  8. Oregon Procedure and Criteria for Hazardous Waste Treatment,...

    Open Energy Info (EERE)

    Oregon Procedure and Criteria for Hazardous Waste Treatment, Storage or Disposal Permits Fact Sheet Jump to: navigation, search OpenEI Reference LibraryAdd to library Permitting...

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

    Office of Environmental Management (EM)

    Confinement Ventilation and Process Gas Treatment FAQS Qualification Card - Confinement Ventilation and Process Gas Treatment A key element for the Department's Technical...

  10. 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

  11. On-Site Wastewater Treatment Systems: Soil Particle Analysis Procedure

    E-Print Network [OSTI]

    Lesikar, Bruce J.

    2005-08-18T23:59:59.000Z

    Soil is an important component of an on-site wastewater treatment system. This publication explains the composition of soils, the sizing of soil particles, and the ways soil particles are analyzed to determine whether a site is suitable for a...

  12. Firearms Qualification Courses Manual

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

    2002-01-17T23:59:59.000Z

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

  13. Ameresco ESCO Qualification Sheet

    Broader source: Energy.gov [DOE]

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

  14. Constellation ESCO Qualification Sheet

    Broader source: Energy.gov [DOE]

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

  15. 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).

  16. J ....... Dlvlelon APOLLO 14 LRRR QUALIF'ICATION

    E-Print Network [OSTI]

    Rathbun, Julie A.

    /~,~~~, ·Yoapace J ....... Dlvlelon APOLLO 14 LRRR QUALIF'ICATION STATUS LIST NO. PAGE DATE IU /l ~ APOLLO 14 LRRR QUALIFICATION 14 15 #12;APOLLO 14 LRRR QUALIFICATION STATUS LIST NO. ATM-867 PAGE REV. NO. A OF I 5 DATE 20 August

  17. AGR-1 Data Qualification Report

    SciTech Connect (OSTI)

    Michael Abbott

    2010-03-01T23:59:59.000Z

    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.

  18. Firearms Qualification Courses Manual

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

    1997-08-21T23:59:59.000Z

    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.

  19. 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...

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

    SciTech Connect (OSTI)

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

    2012-05-16T23:59:59.000Z

    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.

  1. Qualification Status List (QSL Package)

    E-Print Network [OSTI]

    Rathbun, Julie A.

    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

  2. Firearms Qualification Courses Manual

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

    1997-07-08T23:59:59.000Z

    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.

  3. Firearms Qualification Courses Manual

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

    1992-12-01T23:59:59.000Z

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

  4. ORISE: Training and Qualification Programs

    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...

  5. 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).

  6. 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).

  7. 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).

  8. 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).

  9. Experience gained from equipment qualification inspections

    SciTech Connect (OSTI)

    Jacobus, M.J.

    1986-01-01T23:59:59.000Z

    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.

  10. Technical Qualification Program Description - Integrated Support...

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

    to begin the 18 month qualification period). Technical Qualification Program Description Revision 2, November 2010 5 The position's inclusion in the TQP is: * Specified in the PD...

  11. 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.

  12. 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.

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

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

    50-2013, Quality Assurance Functional Area Qualification Standard by Administrator The Quality Assurance (QA) Functional Area Qualification Standard (FAQS) establishes common...

  14. 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.

  15. 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.

  16. 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.

  17. 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).

  18. 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).

  19. 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).

  20. 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).

  1. 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).

  2. 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).

  3. SU-E-J-162: Quality Assurance Procedures for MR Guided Focused Ultrasound Treatment of Bone Metastasis

    SciTech Connect (OSTI)

    Chen, L; Chen, X; Wang, B; Gupta, R; Ma, C [Fox Chase Cancer Center, Philadelphia, PA (United States)

    2014-06-01T23:59:59.000Z

    Purpose: The purpose of this work is to develop and verify our quality assurance (QA) procedures to ensure the safety and efficacy of MR-guided focused ultrasound (MRgFUS) treatment of bone metastases. Methods: A practical QA program was developed. Monthly and daily QA (DQA) procedures were performed. The major QA items included the checks of the machine hardware, software and patient safety features. Briefly, these checks/tests include: 1) the cooling system reservoir and treatment table; 2) power to the treatment table; 3) the MR coil; 4) the transducer position with MRI; 5) image display on the treatment work station; 6) the effective focal spot in 3 directions using MR thermometry; and 7) all the safety devices including a sonication lamp, and the emergency stop-sonication switches. In order to avoid patient skin burn, it is important to remove gas bubbles in the interfaces between the treatment table and the gel pad, and the gel pad and patients skin during the patient setup. Our QA procedures have been verified and evaluated through patient treatments. Seven patients with scapula, humeral head, sacrum, ilium, pubic ramus and acetabular bone metastases were treated using MRgFUS. Results: Our study showed that all seven patients tolerated the MRgFUS treatment well. No skin toxicity or other complications were observed. The pain score (0–10) using the visual analog scale (VAS) was significantly reduced from 8.0 ± 1.1 before treatment to 4.7 ± 3.0, 3.0 ± 1.5, 3.2 ± 2.8 and 3.4 ± 1.5 at one day, one month, two months and three months after the MRgFUS treatment, respectively. Conclusion: We demonstrated that with the appropriate QA procedures, MRgFUS is a safe, effective and noninvasive treatment modality for palliation of bone metastases.

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

    SciTech Connect (OSTI)

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

    2012-03-06T23:59:59.000Z

    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.

  5. Issues in the flight qualification of a space power reactor

    SciTech Connect (OSTI)

    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

    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.

  6. 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...

  7. 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...

  8. ITER Central Solenoid Coil Insulation Qualification

    SciTech Connect (OSTI)

    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

    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.

  9. ITER CENTRAL SOLENOID COIL INSULATION QUALIFICATION

    SciTech Connect (OSTI)

    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

    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.

  10. Protective Force Firearms Qualification Courses

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

    points; Protective Force Firearms Qualification Courses Section A Appendix 4 July 2011 4-3 d. a projectile print within or cutting the outer ring is 2 points; and e. a projectile...

  11. 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).

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

    SciTech Connect (OSTI)

    Cook, J.F.

    1987-10-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Not Available

    1980-01-01T23:59:59.000Z

    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.

  14. CONSIDERATIONS FOR THE TREATMENT OF COMPUTERIZED PROCEDURES IN HUMAN RELIABILITY ANALYSIS

    SciTech Connect (OSTI)

    Ronald L. Boring; David I. Gertman

    2012-07-01T23:59:59.000Z

    Computerized procedures (CPs) are an emerging technology within nuclear power plant control rooms. While CPs have been implemented internationally in advanced control rooms, to date no US nuclear power plant has implemented CPs in its main control room. Yet, CPs are a reality of new plant builds and are an area of considerable interest to existing plants, which see advantages in terms of easier records management by omitting the need for updating hardcopy procedures. The overall intent of this paper is to provide a characterization of human reliability analysis (HRA) issues for computerized procedures. It is beyond the scope of this document to propose a new HRA approach or to recommend specific methods or refinements to those methods. Rather, this paper serves as a review of current HRA as it may be used for the analysis and review of computerized procedures.

  15. Optimization Online - Constraint Qualification Failure in Second ...

    E-Print Network [OSTI]

    Hassan L. Hijazi

    2014-07-22T23:59:59.000Z

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

  16. Committee on Educational Policy MAJOR QUALIFICATION POLICY

    E-Print Network [OSTI]

    California at Santa Cruz, University of

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

  17. 4~APOLLO 14 LRRR QUALIFICATION STATUS LIST

    E-Print Network [OSTI]

    Rathbun, Julie A.

    4~APOLLO 14 LRRR QUALIFICATION STATUS LIST NO. R!V.NO. ATM-867 PAGE 1 OF 6 DATI! April 29, 1970APOLLO 14 LRRR QUALIFICATION STATUS LIST CON!TENTS Title INTRODUCTION PAGI 2 OP 6 DATI! April 29, 1970 Page #12;APOLLO 14 LRRR QUALIFICATION STATUS LIST ATM-867 flAGI! 3 OP

  18. Investigations into the Optimization of Multi-Source Strength Brachytherapy Treatment Procedures

    SciTech Connect (OSTI)

    D. L. Henderson; S. Yoo; B.R. Thomadsen

    2002-09-30T23:59:59.000Z

    The goal of this project is to investigate the use of multi-strength and multi-specie radioactive sources in permanent prostate implant brachytherapy. In order to fulfill the requirement for an optimal dose distribution, the prescribed dose should be delivered to the target in a nearly uniform dose distribution while simultaneously sparing sensitive structures. The treatment plan should use a small number of needles and sources while satisfying the treatment requirements. The hypothesis for the use of multi-strength and/or multi-specie sources is that a better treatment plan using fewer sources and needles could be obtained than by treatment plans using single-strength sources could reduce the overall number of sources used for treatment. We employ a recently developed greedy algorithm based on the adjoint concept as the optimization search engine. The algorithm utilizes and ''adjoint ratio'', which provides a means of ranking source positions, as the pseudo-objective function. It ha s been shown that the greedy algorithm can solve the optimization problem efficiently and arrives at a clinically acceptable solution in less than 10 seconds. Our study was inclusive, that is there was no combination of sources that clearly stood out from the others and could therefore be considered the preferred set of sources for treatment planning. Source strengths of 0.2 mCi (low), 0.4 mCi (medium), and 0.6 mCi (high) of {sup 125}I in four different combinations were used for the multi-strength source study. The combination of high- and medium-strength sources achieved a more uniform target dose distribution due to few source implants whereas the combination of low-and medium-strength sources achieved better sparing of sensitive tissues including that of the single-strength 0.4 mCi base case. {sup 125}I at 0.4 mCi and {sup 192}Ir at 0.12 mCi and 0.25 mCi source strengths were used for the multi-specie source study. This study also proved inconclusive , Treatment plans using a combination of two 0.12 mCi {sup 192}Ir sources and {sup 125}I sources or a combination of two 0.25 mCi {sup 192}Ir sources and {sup 125}I sources did not have better target and sensitive structures DVHs than that of the single specie {sup 125}I 0.4 mCi base case. However, because of the high dose delivered by a {sup 192}Ir source, the multi-specie treatment plan required fewer sources and needles and hence is less invasive than the treatment plan for the 0/4 mCi {sup 125}I base case.

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

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

    6.2 Admin Chg 1, Personnel Selection, Training, Qualification, and Certification Requirements for DOE Nuclear Facilities by Sam Rosenbloom Functional areas: Administrative Change,...

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

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

    6.2, Personnel Selection, Training, Qualification, and Certification Requirements for DOE Nuclear Facilities by Sam Rosenbloom Functional areas: Safety, The order establishes...

  1. Advanced Qualification of Additive Manufacturing Workshop

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

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

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

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

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

  3. 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).

  4. History of IEC Qualification Standards (Presentation)

    SciTech Connect (OSTI)

    Wohlhgemuth, J.

    2011-07-01T23:59:59.000Z

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

  5. 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).

  6. 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.

  7. 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.

  8. FAQS Qualification Card- Civil Structural Engineering

    Broader source: Energy.gov [DOE]

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

  9. 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).

  10. 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).

  11. FAQS Qualification Card – Safety Software Quality Assurance

    Broader source: Energy.gov [DOE]

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

  12. FAQS Qualification Card – 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).

  13. 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).

  14. 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).

  15. 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).

  16. Geometric Qualification of Production Parts

    SciTech Connect (OSTI)

    J. A. Bradley

    2005-09-30T23:59:59.000Z

    Computer Aided Design (CAD) is a commonly utilized software tool to conceptualize and create the part designs that are then used as input for product definition, or for the manufacture of production parts within commercial industry and, more specifically, at the Kansas City Plant (KCP). However, data created on CAD systems is, at times, unable to regenerate within the originating CAD system or be shared or translated for use by a dissimilar CAD system. Commercial software has been developed to help identify or qualify these difficulties that occur in the usage of this data. This project reviewed the different commercial software packages available for the activity of qualification and made recommendations for availability and use in the design processes at the KCP prior to the release of the product definition.

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

    Office of Environmental Management (EM)

    stress tests beyond the qualification test levels, which are necessary to predict PV module wear-out. The commercial success of PVs is ultimately based on the long-term...

  18. 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).

  19. Seismic equipment qualification at Rocky Flats Plant: Lessons learned

    SciTech Connect (OSTI)

    Peregoy, W.; Herring, K.

    1993-08-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Sterling, S.G., Westinghouse Hanford

    1996-07-01T23:59:59.000Z

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

  1. Changing nature of equipment and parts qualification

    SciTech Connect (OSTI)

    Bucci, R.M.

    1988-01-01T23:59:59.000Z

    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.

  2. AGC-2 Irradiation Data Qualification Final Report

    SciTech Connect (OSTI)

    Laurence C. Hull

    2012-07-01T23:59:59.000Z

    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

  3. April 2002, L. Henn-Lecordier LAMP general operating procedures 1 Laboratory for Advanced Materials Processing

    E-Print Network [OSTI]

    Rubloff, Gary W.

    written request ­ Receive safety training from DES ­ Lab orientation with the lab manager ­ Equipment training and qualification #12;April 2002, L. Henn-Lecordier LAMP general operating procedures 9 LAMP "10

  4. Achieving agility through parameter space qualification

    SciTech Connect (OSTI)

    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

    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.

  5. AGR-1 Data Qualification Interim Report

    SciTech Connect (OSTI)

    Machael Abbott

    2009-08-01T23:59:59.000Z

    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.

  6. The Adjoint Method for The Optimization of Brachytherapy and Radiotherapy Patient Treatment Planning Procedures Using Monte Carlo Calculations

    SciTech Connect (OSTI)

    D.L. Henderson; S. Yoo; M. Kowalok; T.R. Mackie; B.R. Thomadsen

    2001-10-30T23:59:59.000Z

    The goal of this project is to investigate the use of the adjoint method, commonly used in the reactor physics community, for the optimization of radiation therapy patient treatment plans. Two different types of radiation therapy are being examined, interstitial brachytherapy and radiotherapy. In brachytherapy radioactive sources are surgically implanted within the diseased organ such as the prostate to treat the cancerous tissue. With radiotherapy, the x-ray source is usually located at a distance of about 1-metere from the patient and focused on the treatment area. For brachytherapy the optimization phase of the treatment plan consists of determining the optimal placement of the radioactive sources, which delivers the prescribed dose to the disease tissue while simultaneously sparing (reducing) the dose to sensitive tissue and organs. For external beam radiation therapy the optimization phase of the treatment plan consists of determining the optimal direction and intensity of beam, which provides complete coverage of the tumor region with the prescribed dose while simultaneously avoiding sensitive tissue areas. For both therapy methods, the optimal treatment plan is one in which the diseased tissue has been treated with the prescribed dose and dose to the sensitive tissue and organs has been kept to a minimum.

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

    SciTech Connect (OSTI)

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

    2000-08-23T23:59:59.000Z

    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.

  8. Safety critical software development qualification

    SciTech Connect (OSTI)

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

    2006-07-01T23:59:59.000Z

    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)

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

    SciTech Connect (OSTI)

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

    1996-12-31T23:59:59.000Z

    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.

  10. RERTR Fuel Developmemt and Qualification Plan

    SciTech Connect (OSTI)

    Dan Wachs

    2007-01-01T23:59:59.000Z

    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.

  11. Historical flight qualifications of space nuclear systems

    SciTech Connect (OSTI)

    Bennett, G.L. [Metaspace Enterprises 5000 Butte Road Emmett, Idaho83617-9500 (United States)

    1997-01-01T23:59:59.000Z

    An overview is presented of the qualification programs for the general-purpose heat source radioisotope thermoelectric generators (GPHS-RTGs) as developed for the Galileo and Ulysses missions; the SNAP-10A space reactor; the Nuclear Engine for Rocket Vehicle Applications (NERVA); the F-1 chemical rocket engine used on the Saturn-V Apollo lunar missions; and the Space Shuttle Main Engines (SSMEs). Some similarities and contrasts between the qualification testing employed on these five programs will be noted. One common thread was that in each of these successful programs there was an early focus on component and subsystem tests to uncover and correct problems. {copyright} {ital 1997 American Institute of Physics.}

  12. High Temperature Materials Interim Data Qualification Report

    SciTech Connect (OSTI)

    Nancy Lybeck

    2010-08-01T23:59:59.000Z

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

  13. 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.

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

    SciTech Connect (OSTI)

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

    2013-04-01T23:59:59.000Z

    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.

  15. 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...

  16. Microsoft Word - advance-qualification-workshop-interim-agenda...

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

    Qualification of Additive Manufacturing Materials using in situ sensors, diagnostics and modeling Sponsored by Los Alamos National Laboratory Institute for Materials Science (IMS)...

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

    Office of Environmental Management (EM)

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

  18. Optimization Online - A cone-continuity constraint qualification and ...

    E-Print Network [OSTI]

    Roberto Andreani

    2015-02-13T23:59:59.000Z

    Feb 13, 2015 ... A cone-continuity constraint qualification and algorithmic consequences. Roberto Andreani(andreani ***at*** ime.unicamp.br) Jose Mario ...

  19. NORTHWESTERN UNIVERSITY Qualification of Autonomous Crack Monitoring Systems

    E-Print Network [OSTI]

    NORTHWESTERN UNIVERSITY Qualification of Autonomous Crack Monitoring Systems A Thesis Submitted Term or Static Testing Equipment Setup.............................................29 Long Term Response.....................................................................33 Dynamic Testing Equipment

  20. 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...

  1. Large Bore Powder Gun Qualification (U)

    SciTech Connect (OSTI)

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

    2012-04-02T23:59:59.000Z

    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.

  2. Safety Management Manual Safety Management Procedures

    E-Print Network [OSTI]

    Kurapov, Alexander

    and Personnel 6.2 New Crew Orientation 6.3 Crane Operator Qualification 6.4 Boat Operations 6.5 A.2 Responsibilities of the Deck Department 7.3 Deck Equipment Responsibilities 7.4 Departure/Arrival Procedures 7.16 Overboarding Equipment 7.17 CTD Operations 1 Feb 2013 1 Dec 2013 1 Dec 2013 1 Dec 2013 1 Feb 2013 1 Feb 2013 1

  3. High-level waste qualification: Managing uncertainty

    SciTech Connect (OSTI)

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

    1993-12-31T23:59:59.000Z

    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.

  4. AVIATION MANAGER QUALIFICATION STANDARD REFERENCE GUIDE

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy China 2015ofDepartmentDepartment of2 of 5) ALARAManager Qualification Standard Reference

  5. AVIATION SAFETY OFFICER QUALIFICATION STANDARD REFERENCE GUIDE

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy China 2015ofDepartmentDepartment of2 of 5) ALARAManager Qualification Standard

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

    SciTech Connect (OSTI)

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

    2014-03-01T23:59:59.000Z

    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.

  7. Department for Education Assessment, Curriculum and General Qualifications

    E-Print Network [OSTI]

    Rambaut, Andrew

    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

  8. 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).

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

    SciTech Connect (OSTI)

    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

    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)

  10. Confinement Ventilation and Process Gas Treatment Functional Area Qualification Standard

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011AT&T, Inc.'sEnergyTexas1.Space DataEnergyCompressedOil, and. NOT MEASUREMENT

  11. Product consistency test and toxicity characteristic leaching procedure results of the ceramic waste form from the electrometallurgical treatment process for spent fuel

    SciTech Connect (OSTI)

    Johnson, S. G.; Adamic, M. L.: DiSanto, T.; Warren, A. R.; Cummings, D. G.; Foulkrod, L.; Goff, K. M.

    1999-11-11T23:59:59.000Z

    The ceramic waste form produced from the electrometallurgical treatment of sodium bonded spent fuel from the Experimental Breeder Reactor-II was tested using two immersion tests with separate and distinct purposes. The product consistency test is used to assess the consistency of the waste forms produced and thus is an indicator of a well-controlled process. The toxicity characteristic leaching procedure is used to determine whether a substance is to be considered hazardous by the Environmental Protection Agency. The proposed high level waste repository will not be licensed to receive hazardous waste, thus any waste forms destined to be placed there cannot be of a hazardous nature as defined by the Resource Conservation and Recovery Act. Results are presented from the first four fully radioactive ceramic waste forms produced and from seven ceramic waste forms produced from cold surrogate materials. The fully radioactive waste forms are approximately 2 kg in weight and were produced wit h salt used to treat 100 driver subassemblies of spent fuel.

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

    SciTech Connect (OSTI)

    Covert, Timothy Todd

    2010-10-01T23:59:59.000Z

    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.

  13. Equipment qualification issues research and resolution: Status report

    SciTech Connect (OSTI)

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

    1986-11-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    P. Sanchez

    2001-05-30T23:59:59.000Z

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

  15. 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...

  16. Emergency Procedures

    Broader source: Energy.gov [DOE]

    Note: This page is pending deletion, please refer to the Safety and health main page for emergency procedure information:

  17. Secondary Waste Cast Stone Waste Form Qualification Testing Plan

    SciTech Connect (OSTI)

    Westsik, Joseph H.; Serne, R. Jeffrey

    2012-09-26T23:59:59.000Z

    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

  18. Workshop on environmental qualification of electric equipment

    SciTech Connect (OSTI)

    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

    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.

  19. AGC-3 Irradiation Data Qualification Final Report

    SciTech Connect (OSTI)

    Laurence Hull

    2014-08-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Muller, M.

    2012-03-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

    Randklev, E.H.

    1993-06-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

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

    2000-06-09T23:59:59.000Z

    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.

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

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

    2001-07-12T23:59:59.000Z

    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

  4. Dossier de qualification Matre de Confrences, section 61

    E-Print Network [OSTI]

    Coupechoux, Marceau

    Dossier de qualification Maître de Conférences, section 61 Marceau Coupechoux Télécom ParisTech, CNRS LTCI 37-39, rue Dareau 75014 Paris marceau.coupechoux@telecom-paristech.fr http'enseignement, de recherche et charges collectives. Marceau COUPECHOUX Télécom ParisTech - Département Informatique

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

    SciTech Connect (OSTI)

    Staehr, T.W., Westinghouse Hanford

    1996-05-02T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Edwards, T; Mahannah, R.

    2011-07-05T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    2012-05-31T23:59:59.000Z

    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

  8. A Declarative Semantics for CLP with Qualification and Proximity

    E-Print Network [OSTI]

    Rodríguez-Artalejo, Mario; 10.1017/S1471068410000323

    2010-01-01T23:59:59.000Z

    Uncertainty in Logic Programming has been investigated during the last decades, dealing with various extensions of the classical LP paradigm and different applications. Existing proposals rely on different approaches, such as clause annotations based on uncertain truth values, qualification values as a generalization of uncertain truth values, and unification based on proximity relations. On the other hand, the CLP scheme has established itself as a powerful extension of LP that supports efficient computation over specialized domains while keeping a clean declarative semantics. In this paper we propose a new scheme SQCLP designed as an extension of CLP that supports qualification values and proximity relations. We show that several previous proposals can be viewed as particular cases of the new scheme, obtained by partial instantiation. We present a declarative semantics for SQCLP that is based on observables, providing fixpoint and proof-theoretical characterizations of least program models as well as an imp...

  9. High Temperature Materials Interim Data Qualification Report FY 2011

    SciTech Connect (OSTI)

    Nancy Lybeck

    2011-08-01T23:59:59.000Z

    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.

  10. Nuclear criticality safety engineer qualification program utilizing SAT

    SciTech Connect (OSTI)

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

    1996-12-31T23:59:59.000Z

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

  11. Plutonium metal and oxide container weld development and qualification

    SciTech Connect (OSTI)

    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

    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.``

  12. Test Cloth Qualification | 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 onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnual Siteof Energy 2, 2015 - JanuaryTank 48H Treatment

  13. Qualification of Innovative High Level Waste Pipeline Unplugging Technologies

    SciTech Connect (OSTI)

    McDaniel, D.; Gokaltun, S.; Varona, J.; Awwad, A.; Roelant, D.; Srivastava, R. [Applied Research Center, Florida International University, Miami, FL (United States)

    2008-07-01T23:59:59.000Z

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

  14. Qualification of NDE personnel in the nuclear industry

    SciTech Connect (OSTI)

    Epps, T.N.

    1984-06-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Binh Pham; Jeff Einerson

    2014-01-01T23:59:59.000Z

    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.

  16. 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).

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

    E-Print Network [OSTI]

    Glasgow, University of

    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

  18. 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.

  19. Qualification tests of materials for spallation neutron sources

    SciTech Connect (OSTI)

    Sommer, W.F.

    1996-12-31T23:59:59.000Z

    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.

  20. Title 43 CFR 3202 Lessee Qualifications | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand Jump to:Ezfeedflag JumpID-f <MaintainedInformationThePty LtdOpen EnergyAct | OpenQualifications

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

    SciTech Connect (OSTI)

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

    2014-06-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    SAMS TL; EDGE JA; SWANBERG DJ; ROBBINS RA

    2011-01-13T23:59:59.000Z

    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.

  3. DOT-7A Type A packaging test and evaluation procedure

    SciTech Connect (OSTI)

    Kelly, D.L., Westinghouse Hanford

    1996-06-13T23:59:59.000Z

    The purpose of this document is to provide guidance for qualifying a DOT-7A Type A packaging for use. WHC qualifies DOT-7A packaging for two purposes. The first is to provide packages for use by WHC (manufacturer-qualified). The second is to provide a contracted service in support of DOE/EM-76 (DOE-qualified). This document includes descriptions of the performance tests, the personnel involved and their qualifications, appropriate safety and quality assurance considerations, and the procedures to be followed when WHC performs the tests (either as the manufacturer, or on behalf of the DOE`s certification program).

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

    SciTech Connect (OSTI)

    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

    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.

  5. Application of Microprocessor-Based Equipment in Nuclear Power Plants - Technical Basis for a Qualification Methodology

    SciTech Connect (OSTI)

    Korsah, K.

    2001-08-24T23:59:59.000Z

    This document (1) summarizes the most significant findings of the ''Qualification of Advanced Instrumentation and Control (I&C) Systems'' program initiated by the Nuclear Regulatory Commission (NRC); (2) documents a comparative analysis of U.S. and European qualification standards; and (3) provides recommendations for enhancing regulatory guidance for environmental qualification of microprocessor-based safety-related systems. Safety-related I&C system upgrades of present-day nuclear power plants, as well as I&C systems of Advanced Light-Water Reactors (ALWRs), are expected to make increasing use of microprocessor-based technology. The Nuclear Regulatory Commission (NRC) recognized that the use of such technology may pose environmental qualification challenges different from current, analog-based I&C systems. Hence, it initiated the ''Qualification of Advanced Instrumentation and Control Systems'' program. The objectives of this confirmatory research project are to (1) identify any unique environmental-stress-related failure modes posed by digital technologies and their potential impact on the safety systems and (2) develop the technical basis for regulatory guidance using these findings. Previous findings from this study have been documented in several technical reports. This final report in the series documents a comparative analysis of two environmental qualification standards--Institute of Electrical and Electronics Engineers (IEEE) Std 323-1983 and International Electrotechnical Commission (IEC) 60780 (1998)--and provides recommendations for environmental qualification of microprocessor-based systems based on this analysis as well as on the findings documented in the previous reports. The two standards were chosen for this analysis because IEEE 323 is the standard used in the U.S. for the qualification of safety-related equipment in nuclear power plants, and IEC 60780 is its European counterpart. In addition, the IEC document was published in 1998, and should reflect any new qualification concerns, from the European perspective, with regard to the use of microprocessor-based safety systems in power plants.

  6. EDS V25 containment vessel explosive qualification test report.

    SciTech Connect (OSTI)

    Rudolphi, John Joseph

    2012-04-01T23:59:59.000Z

    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.

  7. DOE Technical Standards Program Procedures, 2009, DOE-TSPP-6

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

    2.1.6 Coordination of Technical Qualification Standards and Information Architecture Standards ......

  8. Technical Qualification Program Self-Assessment Report- Los Alamos Field Office- FY15

    Broader source: Energy.gov [DOE]

    The FY15 self-assessment of the Technical Qualifications and Federal Technical Capability program was conducted to provide Los Alamos Field Office (NA-LA) management specific information related to effectiveness of the documentation and implementation of these programs.

  9. 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.

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

    Office of Environmental Management (EM)

    of the TQP self-assessment was to evaluate the personnel, procedures, and management control systems that demonstrate an effective program for ensuring the technical...

  11. Technical Qualification Program Self-Assessment Report- Los Alamos Field Office- 2014

    Broader source: Energy.gov [DOE]

    This self-assessment for the Verification of the Closure of Federal Training & Qualification Deficiencies was conducted to provide Los Alamos Field Office (NA-LA) management specific information related to effectiveness of the closure actions for Federal Training and Qualification (T &Q) deficiencies identified by a recent self-assessment and by a CDNS Biennial review. The conclusion of this assessment is that most deficiencies have corrective actions assigned that are effectively completed and adequately documented.

  12. Certification and Listing Process and Procedures Workshop

    Broader source: Energy.gov [DOE]

    Slides from the U.S. Department of Energy Hydrogen Component and System Qualification Workshop held November 4, 2010 in Livermore, CA.

  13. Technology transfer equipment qualification methodology for shelf life determination

    SciTech Connect (OSTI)

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

    1995-08-01T23:59:59.000Z

    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.

  14. "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,...

  15. Computerized procedures system

    SciTech Connect (OSTI)

    Lipner, Melvin H. (Monroeville, PA); Mundy, Roger A. (North Huntingdon, PA); Franusich, Michael D. (Upper St. Clair, PA)

    2010-10-12T23:59:59.000Z

    An online data driven computerized procedures system that guides an operator through a complex process facility's operating procedures. The system monitors plant data, processes the data and then, based upon this processing, presents the status of the current procedure step and/or substep to the operator. The system supports multiple users and a single procedure definition supports several interface formats that can be tailored to the individual user. Layered security controls access privileges and revisions are version controlled. The procedures run on a server that is platform independent of the user workstations that the server interfaces with and the user interface supports diverse procedural views.

  16. Centralized maintenance procedures

    SciTech Connect (OSTI)

    Barber, J.R.

    1994-02-01T23:59:59.000Z

    In 1989, shortly after Westinghouse Hanford Company (WHC) assumed maintenance responsibilities for the Hanford site, a Department of Energy (DOE) maintenance audit found that field (working level) maintenance procedures and procedure practices of the facilities scattered across Hanford`s 560 square miles varied as greatly as the locations of those facilities. In some of the audited facilities there were few or no procedures; in others, procedures conflicted with or were redundant to procedures at other facilities. This document presents current efforts to centralize maintenance procedures.

  17. Federal Agency NEPA Procedures

    Broader source: Energy.gov [DOE]

    Each Federal agency is required to develop NEPA procedures that supplement the CEQ Regulations. Developed in consultation with CEQ, Federal agency NEPA procedures must meet the standards in the CEQ...

  18. Medical Student Procedure Guide

    E-Print Network [OSTI]

    Chapman, Michael S.

    20132014 O.H.S.U. Medical Student Procedure Guide #12;2013-2014 Medical Student Procedure Guide 1 Oregon Health & Science University School of Medicine - Medical Student Procedure Guide Welcome This is an exciting time to be in medicine. Advances in the sciences basic to the study and practice of medicine

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

    SciTech Connect (OSTI)

    NONE

    1996-03-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Peters, T. B.

    2013-02-26T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    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

    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.

  2. 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]

    American Society for Testing and Materials. Philadelphia

    2007-01-01T23:59:59.000Z

    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.

  3. Qualification test for the flexible receiver. Revision 2

    SciTech Connect (OSTI)

    Tedeschi, D.J.

    1994-12-12T23:59:59.000Z

    This document provides the test plan and procedures to certify and design verify the 42{double_prime} and 4{double_prime}-6{double_prime} Flexible Receiver as a safety class 3 system. The Flexible Receiver will be used by projects W-151 and W-320 for removing equipment from tanks C-106 and AZ-101.

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

    SciTech Connect (OSTI)

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

    2011-03-14T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    2014-06-01T23:59:59.000Z

    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.

  6. Text Delegation Procedures

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

    Procedures for Line Managers' Delegations of Authority when proposing new delegations, redelegating existing delegation, proposing an amendment, rescinding a delegation, and when a delegation is not needed.

  7. Testing of Small Graphite Samples for Nuclear Qualification

    SciTech Connect (OSTI)

    Julie Chapman

    2010-11-01T23:59:59.000Z

    Accurately determining the mechanical properties of small irradiated samples is crucial to predicting the behavior of the overal irradiated graphite components within a Very High Temperature Reactor. The sample size allowed in a material test reactor, however, is limited, and this poses some difficulties with respect to mechanical testing. In the case of graphite with a larger grain size, a small sample may exhibit characteristics not representative of the bulk material, leading to inaccuracies in the data. A study to determine a potential size effect on the tensile strength was pursued under the Next Generation Nuclear Plant program. It focuses first on optimizing the tensile testing procedure identified in the American Society for Testing and Materials (ASTM) Standard C 781-08. Once the testing procedure was verified, a size effect was assessed by gradually reducing the diameter of the specimens. By monitoring the material response, a size effect was successfully identified.

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

    SciTech Connect (OSTI)

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

    2012-12-20T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    2012-12-11T23:59:59.000Z

    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.

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

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

    2010-04-21T23:59:59.000Z

    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.

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

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

    2010-04-21T23:59:59.000Z

    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.

  12. 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.

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

    E-Print Network [OSTI]

    Walker, Matthew P.

    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

  14. 1. Holder of the Qualification 1.1 Surname / 1.2. First Name

    E-Print Network [OSTI]

    Schubart, Christoph

    Credit Points) 3.3. Access Requirements Higher Education Entrance Qualification (HEEQ), General; or foreign equivalent. After 12 to 13 years of schooling the HEEQ gives access to all higher education of linguis- tics as well as sociolinguistics and endows the student with the skills to conduct empirical

  15. 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.

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

    E-Print Network [OSTI]

    Rivest, Ronald L.

    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

  17. EML procedures manual

    SciTech Connect (OSTI)

    Volchok, H.L.; de Planque, G. (eds.)

    1982-01-01T23:59:59.000Z

    This manual contains the procedures that are used currently by the Environmental Measurements Laboratory of the US Department of Energy. In addition a number of analytical methods from other laboratories have been included. These were tested for reliability at the Battelle, Pacific Northwest Laboratory under contract with the Division of Biomedical and Environmental Research of the AEC. These methods are clearly distinguished. The manual is prepared in loose leaf form to facilitate revision of the procedures and inclusion of additional procedures or data sheets. Anyone receiving the manual through EML should receive this additional material automatically. The contents are as follows: (1) general; (2) sampling; (3) field measurements; (4) general analytical chemistry; (5) chemical procedures; (6) data section; (7) specifications.

  18. IEEE TRANSACTIONS ON NUCLEAR SCIENCE, VOL. 52, NO. 4, AUGUST 2005 1061 Radiation Qualification of Electronics Components

    E-Print Network [OSTI]

    Fukunaga, Chikara

    IEEE TRANSACTIONS ON NUCLEAR SCIENCE, VOL. 52, NO. 4, AUGUST 2005 1061 Radiation Qualification@comp.metro-u.ac.jp). T. Sakuma is with the Tokyo University of Agriculture and Engineering, Ko- ganei 183-8538, Japan

  19. Fixpoint & Proof-theoretic Semantics for CLP with Qualification and Proximity

    E-Print Network [OSTI]

    Rodríguez-Artalejo, Mario

    2010-01-01T23:59:59.000Z

    Uncertainty in Logic Programming has been investigated during the last decades, dealing with various extensions of the classical LP paradigm and different applications. Existing proposals rely on different approaches, such as clause annotations based on uncertain truth values, qualification values as a generalization of uncertain truth values, and unification based on proximity relations. On the other hand, the CLP scheme has established itself as a powerful extension of LP that supports efficient computation over specialized domains while keeping a clean declarative semantics. In this report we propose a new scheme SQCLP designed as an extension of CLP that supports qualification values and proximity relations. We show that several previous proposals can be viewed as particular cases of the new scheme, obtained by partial instantiation. We present a declarative semantics for SQCLP that is based on observables, providing fixpoint and proof-theoretical characterizations of least program models as well as an im...

  20. Seismic qualification of equipment by means of probabilistic risk assessment. [PWR

    SciTech Connect (OSTI)

    Azarm, M.A.; Farahzad, P.; Boccio, J.L.

    1982-01-01T23:59:59.000Z

    Upon the sponsorship of the Equipment Qualification Branch (EQB) of NRC, Brookhaven National Laboratory (BNL) has utilized a risk-based approach for identifying, in a generic fashion, seismically risk-sensitive equipment. It is anticipated that the conclusions drawn therefrom and the methodology employed will, in part, reconcile some of the concerns dealing with the seismic qualification of equipment in operating plants. The approach taken augments an existing sensitivity analysis, based upon the WASH-1400 Reactor Safety Study (RSS), by accounting for seismicity and component fragility with the Kennedy model and by essentially including the requisite seismic data presented in the Zion Probabilistic Safety Study (ZPSS). Parametrically adjusting the seismic-related variables and ascertaining their effects on overall plant risk, core-melt probability, accident sequence probability, etc., allows one to identify those seismically risk-sensitive systems and equipment. This paper describes the approach taken and highlights the results obtained thus far for a hypothetical pressurized water reactor (PWR).

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

    SciTech Connect (OSTI)

    Wohlgemuth, J. H.; Kurtz, S.

    2011-02-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    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

    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.

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

    SciTech Connect (OSTI)

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

    2013-09-25T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Peeler, D.

    2013-06-27T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    NONE

    1996-03-01T23:59:59.000Z

    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.

  6. 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.

  7. FAQS Qualification Card - Safeguards and Security | 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 DataDepartment of Energy Your Density Isn't YourTransport in Representative Geologic MediaTreatment | Department ofMechanicalSafeguards and

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

    SciTech Connect (OSTI)

    NONE

    1996-03-01T23:59:59.000Z

    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.

  9. Policy Procedure Administrative Directive Title: _____________________________________

    E-Print Network [OSTI]

    Northern British Columbia, University of

    Policy ­ Procedure ­ Administrative Directive Title: _____________________________________ Policy-President _____________ See also: Related Policies, Procedures and Agreements: Relevant Legislation and Regulations: ____________________________________________________________________________ Background and Purpose: ____________________________________________________________________________ Policy

  10. Energy Metering Audit Procedure

    E-Print Network [OSTI]

    Whitaker, W. S.

    Energy Meterilg Audtt Procedure Wiliam S Whitaker Engineering Specialist T X E INC. laPorte Texas INTROOUCI'ION This paper describes the recent audit of the utility distriooticn meters in a petrochanica1 plant. These meters measure the steam... audit Will also identify losses in the distriooticn eMrtem itself. '!he results of the audit can be used to recx:umand charYJes in operatin] procedures ~th respect to energy soorces. In aci:iiticn, ,the audit oou1d \\.Il'1COVer prob1ans...

  11. BOMB THREAT CALL PROCEDURES

    E-Print Network [OSTI]

    Guo, Ting

    THREAT CALL PROCEDURES BOMB THREAT CHECKLIST Date: Time: Time Caller Phone Number Where Hung Up: Call Received:Most bomb threats are received by phone. Bomb threats are serious until proven otherwise. Act threat is received by phone: 1. Remain calm. Keep the caller on the line for as long as possible. DO

  12. BOMB THREAT CALL PROCEDURES

    E-Print Network [OSTI]

    Boyce, Richard L.

    BOMB THREAT CALL PROCEDURES WHO TO CONTACT (select one) · Follow your local guidelines · Federal Protective Service (FPS) Police 1-877-4-FPS-411 (1-877-437-7411) · 911 Most bomb threats are received by phone. Bomb threats are serious until proven otherwise. Act quickly, but remain calm and obtain

  13. ACADEMIC PROGRAM PROCEDURE MANUAL

    E-Print Network [OSTI]

    Fay, Noah

    1 ACADEMIC PROGRAM REVIEW PROCEDURE MANUAL 2014-2015 Office of the Senior Vice President Tucson, AZ 85721 #12;2 ACADEMIC PROGRAM REVIEW MANAGEMENT TEAM Web Site for Academic Program Review http Educational Policy Studies & Practice Spanish and Portuguese Electrical & Computer Engineering Teaching

  14. PHYSICAL PLANT POLICY & PROCEDURE

    E-Print Network [OSTI]

    Fernandez, Eduardo

    PHYSICAL PLANT POLICY & PROCEDURE TITLE PHYSICAL PLANT HIGH VOLTAGE PREVENTIVE MAINTENANCE OBJECTIVE AND PURPOSE To establish a consistent policy of performing Preventive Maintenance on high voltage by the G.S.A. Preventive Maintenance sections E- 29 (high voltage oil circuit breaker), E-32 (high voltage

  15. Refinery Energy Profiling Procedure

    E-Print Network [OSTI]

    Maier, R. W.

    1981-01-01T23:59:59.000Z

    This paper discusses a four-step procedure developed with support from the U.S. Department of Energy for preparing energy profiles for a refinery, for a single unit, or for an individual piece of equipment. The four steps are preparation, data...

  16. HASL procedures manual

    SciTech Connect (OSTI)

    Not Available

    1980-08-01T23:59:59.000Z

    Addition and corrections to the following sections of the HASL Procedures Manual are provided: Table of Contents; Bibliography; Fallout Collection Methods; Wet/Dry Fallout Collection; Fluoride in Soil and Sediment; Strontium-90; Natural Series; Alpha Emitters; and Gamma Emitters. (LK)

  17. Refinery Energy Profiling Procedure 

    E-Print Network [OSTI]

    Maier, R. W.

    1981-01-01T23:59:59.000Z

    This paper discusses a four-step procedure developed with support from the U.S. Department of Energy for preparing energy profiles for a refinery, for a single unit, or for an individual piece of equipment. The four steps are preparation, data...

  18. Pollutant Assessments Group Procedures Manual

    SciTech Connect (OSTI)

    Chavarria, D.E.; Davidson, J.R.; Espegren, M.L.; Kearl, P.M.; Knott, R.R.; Pierce, G.A.; Retolaza, C.D.; Smuin, D.R.; Wilson, M.J.; Witt, D.A. (Oak Ridge National Lab., TN (USA)); Conklin, N.G.; Egidi, P.V.; Ertel, D.B.; Foster, D.S.; Krall, B.J.; Meredith, R.L.; Rice, J.A.; Roemer, E.K. (Oak Ridge Associated Universities, Inc., TN (USA))

    1991-02-01T23:59:59.000Z

    This procedures manual combines the existing procedures for radiological and chemical assessment of hazardous wastes used by the Pollutant Assessments Group at the time of manuscript completion (October 1, 1990). These procedures will be revised in an ongoing process to incorporate new developments in hazardous waste assessment technology and changes in administrative policy and support procedures. Format inconsistencies will be corrected in subsequent revisions of individual procedures.

  19. Implementing MSE 2000: Procedures

    E-Print Network [OSTI]

    Brown, M.; Adams, J.

    experts, technical writers, and subject matter experts, who will not continue on the MSE team. These experts fill a need when the management system is initiated that is completed during the implementation phase. Select MSE Team After... represent the most effective and efficient practice. By including technical writers and subject matter experts on the team, procedure/instruction writing will be hastened and enhanced. SYSTEM APPRAISAL During the system appraisal phase, the MSE 2000...

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

    SciTech Connect (OSTI)

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

    2011-11-16T23:59:59.000Z

    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.

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

    E-Print Network [OSTI]

    Garion, C

    2013-01-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

    McCoskey, Jacob K.

    2014-01-22T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Oji, L. N.

    2013-03-07T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Peters, T.; Fink, S.

    2012-03-26T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    W. Ken Sowder

    2004-02-01T23:59:59.000Z

    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.

  6. UNIVERSITY OF MANITOBA Procedures: ASBESTOS MANAGEMENT PROGRAM PROCEDURE

    E-Print Network [OSTI]

    Major, Arkady

    UNIVERSITY OF MANITOBA PROCEDURE Procedures: ASBESTOS MANAGEMENT PROGRAM PROCEDURE Parent Policy relevant to management and control of asbestos-containing building materials known to be present throughout be made on a regular and required basis, in consultation with the Asbestos Management Program Committee

  7. Surface cleanliness measurement procedure

    DOE Patents [OSTI]

    Schroder, Mark Stewart (Hendersonville, NC); Woodmansee, Donald Ernest (Simpsonville, SC); Beadie, Douglas Frank (Greenville, SC)

    2002-01-01T23:59:59.000Z

    A procedure and tools for quantifying surface cleanliness are described. Cleanliness of a target surface is quantified by wiping a prescribed area of the surface with a flexible, bright white cloth swatch, preferably mounted on a special tool. The cloth picks up a substantial amount of any particulate surface contamination. The amount of contamination is determined by measuring the reflectivity loss of the cloth before and after wiping on the contaminated system and comparing that loss to a previous calibration with similar contamination. In the alternative, a visual comparison of the contaminated cloth to a contamination key provides an indication of the surface cleanliness.

  8. LSU/CAMD Procedure

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes |Is Your Home asLCLS Experimental RunProcedure Doc. ID:

  9. ARM - Publications Procedures

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625govInstrumentstdmadap Documentation TDMADAP :ProductsVaisala CL51 ceilometergovPublicationsPublications Procedures

  10. Thermal oxidation procedure PREPARATION........................................................................................................................................... 2

    E-Print Network [OSTI]

    Hochberg, Michael

    procedure - 2 - Preparation. The preparation procedure sets up the power, gas supplies, cooling water, (DI to check all the supplies. Cooling water Gas supplies Routing DI water for wet oxidation We start........................................................................................................................................... 2 Step 1 Turn on the cooling water

  11. Motor Vehicle Record Procedure Objective

    E-Print Network [OSTI]

    Kirschner, Denise

    Motor Vehicle Record Procedure Objective Outline the procedure for obtaining motor vehicle record (MVR) through Fleet Services. Vehicle Operator Policy 3. Operators with 7 or more points on their motor vehicle record

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

    SciTech Connect (OSTI)

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

    1988-11-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

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

    2002-02-25T23:59:59.000Z

    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.

  14. Calibration Requirements and Procedures for

    E-Print Network [OSTI]

    Tuceryan, Mihran

    Calibration Requirements and Procedures for Augmented Reality Mihran Tuceryan Douglas S. Greer Ross Graphics, Sept 1995) Calibration Requirements and Procedures for Augmented Reality Mihran Tuceryan Douglas of calibration procedures are necessary so that the location and parameters of each of the system components

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

    SciTech Connect (OSTI)

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

    2013-08-01T23:59:59.000Z

    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.

  16. Environmental qualification and functional issues for microprocessor-based reactor protection systems

    SciTech Connect (OSTI)

    Korsah, K.; Kisner, R.; Wood, R.T. [Oak Ridge National Lab., TN (United States); Antonescu, C. [Nuclear Regulatory Commission, Rockville, MD (United States)

    1992-12-01T23:59:59.000Z

    Issues of obsolescence and lack of intrastructural 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. This movement away from analog can be expected to increase in advanced light-water reactors (ALWRs), which will make extensive use of fiber optic transmission, multiplexing techniques, and microprocessor-based technology. Although these technologies have several advantages and, in fact, have been in widespread use in the non-nuclear industry for several years, their application to safety-related systems in nuclear power plants raises key issues relating to the systems` environmental and functional reliability. For example, does the new hardware introduce additional system aging degradation mechanisms that could adversely impact the safety of the plant? Do the systems introduce the possibility of new and different malfunction scenarios or increase the probability of common-mode failures that could reduce the reliability of the safety system?. Are current environmental qualification standards adequate for microprocessor-based I&C systems? Accordingly in 1991 the Nuclear Regulatory Commission (NRC) initiated the qualification of advanced Instrumentation and Control Systems program at ORNL to investigate issues that may arise with the use of advanced digital I&C in ALWRs. The results of our studies to date are summarized in this paper.

  17. Environmental qualification and functional issues for microprocessor-based reactor protection systems

    SciTech Connect (OSTI)

    Korsah, K.; Kisner, R.; Wood, R.T. (Oak Ridge National Lab., TN (United States)); Antonescu, C. (Nuclear Regulatory Commission, Rockville, MD (United States))

    1992-01-01T23:59:59.000Z

    Issues of obsolescence and lack of intrastructural 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. This movement away from analog can be expected to increase in advanced light-water reactors (ALWRs), which will make extensive use of fiber optic transmission, multiplexing techniques, and microprocessor-based technology. Although these technologies have several advantages and, in fact, have been in widespread use in the non-nuclear industry for several years, their application to safety-related systems in nuclear power plants raises key issues relating to the systems' environmental and functional reliability. For example, does the new hardware introduce additional system aging degradation mechanisms that could adversely impact the safety of the plant Do the systems introduce the possibility of new and different malfunction scenarios or increase the probability of common-mode failures that could reduce the reliability of the safety system . Are current environmental qualification standards adequate for microprocessor-based I C systems Accordingly in 1991 the Nuclear Regulatory Commission (NRC) initiated the qualification of advanced Instrumentation and Control Systems program at ORNL to investigate issues that may arise with the use of advanced digital I C in ALWRs. The results of our studies to date are summarized in this paper.

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

    SciTech Connect (OSTI)

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

    2012-08-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

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

    2012-08-01T23:59:59.000Z

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

  20. Princeton Plasma Physics Laboratory D-SITE Procedure

    E-Print Network [OSTI]

    Princeton Plasma Physics Laboratory

    Walkdown USQD (OP-AD-63) Independent Review Master Equip. List Mod (OP-AD-112) ES&H Review (NEPA, IH, etc Qualification and Requalification" 3.6 TR-006, "Establishing Qualification and Certification Requirements" 4.0 DEFINITIONS 4.1 Accessor - persons responsible for NSTX diagnostics, computer equipment or other ancilliary

  1. Utrecht University Academic Integrity Complaints Procedure This complaints procedure follows the national Model Complaints Procedure Academic

    E-Print Network [OSTI]

    Utrecht, Universiteit

    integrity or its researchers and guarantees it will investigate all well-founded suspicions of misconduct1 Utrecht University Academic Integrity Complaints Procedure This complaints procedure follows the national Model Complaints Procedure Academic Integrity of the joint Dutch universities. The model

  2. Part 1, Use of seismic experience and test data to show ruggedness of equipment in nuclear power plants; Part 2, Review procedure to assess seismic ruggedness of cantilever bracket cable tray supports

    SciTech Connect (OSTI)

    Kennedy, R.P. (Structural Mechanics Consulting, Inc., Yorba Linda, CA (United States)); von Riesemann, W.A. (Sandia National Labs., Albuquerque, NM (United States)); Wyllie, L.A. Jr. (Degenkolb (H.J.) Associates, San Francisco, CA (United States)); Schiff, A.J. (Stanford Univ., CA (United States)); Ibanez, P. (Anco Engineers, Inc., Culver City, CA (United States))

    1992-06-01T23:59:59.000Z

    In December 1980, the US Nuclear Regulatory Commission (NRC) designated Seismic Qualification of Equipment in Operating Plants'' as an Unresolved Safety Issue (USI), A-46. The objective of USI A-46 is to develop alternative seismic qualification methods and acceptance criteria that can be used to assess the capability of mechanical and electrical equipment in operating nuclear power plants to perform the intended safety functions. A group of affected utilities formed the Seismic Qualification Utility Group (SQUG) to work with the NRC in developing a program methodology to enable resolution of the A-46 issue. To assist in developing a program methodology, SQUG and the NRC jointly selected and supported a five-member Senior Seismic Review and Advisory Panel (SSRAP) in June 1983 to make an independent assessment of whether certain classes of equipment in operating nuclear power plants in the United States have demonstrated sufficient ruggedness in past earthquakes so as to render an explicit seismic qualification unnecessary. SSRAP operated as an independent review body with all of its findings submitted concurrently to both SQUG and the NRC. During their period of involvement, SSRAP issued several draft reports on their conclusions. This document contains the final versions of these reports; namely, Use of Seismic Experience and Test Data to Show Ruggedness of Equipment in Nuclear Power Plants,'' dated February 1991 and Review Procedure to Assess Seismic Ruggedness of Cantilever Bracket Cable Tray Supports,'' dated March 1, 1991.

  3. Part 1, Use of seismic experience and test data to show ruggedness of equipment in nuclear power plants; Part 2, Review procedure to assess seismic ruggedness of cantilever bracket cable tray supports

    SciTech Connect (OSTI)

    Kennedy, R.P. [Structural Mechanics Consulting, Inc., Yorba Linda, CA (United States); von Riesemann, W.A. [Sandia National Labs., Albuquerque, NM (United States); Wyllie, L.A. Jr. [Degenkolb (H.J.) Associates, San Francisco, CA (United States); Schiff, A.J. [Stanford Univ., CA (United States); Ibanez, P. [Anco Engineers, Inc., Culver City, CA (United States)

    1992-06-01T23:59:59.000Z

    In December 1980, the US Nuclear Regulatory Commission (NRC) designated ``Seismic Qualification of Equipment in Operating Plants`` as an Unresolved Safety Issue (USI), A-46. The objective of USI A-46 is to develop alternative seismic qualification methods and acceptance criteria that can be used to assess the capability of mechanical and electrical equipment in operating nuclear power plants to perform the intended safety functions. A group of affected utilities formed the Seismic Qualification Utility Group (SQUG) to work with the NRC in developing a program methodology to enable resolution of the A-46 issue. To assist in developing a program methodology, SQUG and the NRC jointly selected and supported a five-member Senior Seismic Review and Advisory Panel (SSRAP) in June 1983 to make an independent assessment of whether certain classes of equipment in operating nuclear power plants in the United States have demonstrated sufficient ruggedness in past earthquakes so as to render an explicit seismic qualification unnecessary. SSRAP operated as an independent review body with all of its findings submitted concurrently to both SQUG and the NRC. During their period of involvement, SSRAP issued several draft reports on their conclusions. This document contains the final versions of these reports; namely, ``Use of Seismic Experience and Test Data to Show Ruggedness of Equipment in Nuclear Power Plants,`` dated February 1991 and ``Review Procedure to Assess Seismic Ruggedness of Cantilever Bracket Cable Tray Supports,`` dated March 1, 1991.

  4. Safe Operating Procedure (Revised 7/11)

    E-Print Network [OSTI]

    Farritor, Shane

    not be allowed in the necropsy area. Personal Protective Equipment Considerations · A rear-closing gown. No one is allowed to use respiratory protection equipment unless they are enrolled in the UNL Respiratory complete annual training and fit-testing, and may be subject to medical qualification. (Created 12

  5. alternative treatment method: Topics by E-print Network

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

    the procedures specified in paragraph (k) of this AD. Dated August 2 Casimir force: an alternative treatment CERN Preprints Summary: The Casimir force between two parallel...

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

    E-Print Network [OSTI]

    Rambaut, Andrew

    : 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

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

    SciTech Connect (OSTI)

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

    2005-09-30T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    2005-09-30T23:59:59.000Z

    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

  9. Oregon Procedure and Criteria for Hazardous Waste Treatment, Storage or

    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 onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere I Geothermal Pwer PlantMunhall,Missouri:Energy Information Fees forInformationPlugging Record

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

    SciTech Connect (OSTI)

    Edwards, T.; Mahannah, R.

    2011-07-05T23:59:59.000Z

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

  11. Procedure Advantages Disadvantages Saphenous Vein

    E-Print Network [OSTI]

    Scott, Robert A.

    Procedure Advantages Disadvantages Saphenous Vein No anesthesia Not asep c Pedal Vein No anesthesia Serial bleeding okay Not asep c Tail Bleeding No anesthesia Serial bleeding okay

  12. Procedure Advantages Disadvantages Saphenous Vein

    E-Print Network [OSTI]

    Scott, Robert A.

    Procedure Advantages Disadvantages Saphenous Vein No anesthesia Not asep c Pedal Vein No anesthesia Serial bleeding okay Not asep c Facial Vein No anesthesia Serial bleeding okay

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

    SciTech Connect (OSTI)

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

    2013-07-08T23:59:59.000Z

    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.

  14. Emergency Procedures for Security Personnel Procedural Steps for Emergency Response

    E-Print Network [OSTI]

    Olsen, Stephen L.

    Tab C Emergency Procedures for Security Personnel Procedural Steps for Emergency Response There are numerous emergency scenarios. Each situation can be unique in and of itself. Officer responses are the primary contact person, coordinator, and controller of all emergency responses. If you are incapacitated

  15. Residential Mail Procedures Residential Mail Services

    E-Print Network [OSTI]

    Buehrer, R. Michael

    Residential Mail Procedures Residential Mail Services 23 Owens Hall Blacksburg, VA 24061 Phone.mailservices.vt.edu #12;Residential Mail Procedures Table of Contents General information.................................................................................8 #12;Residential Mail Procedures The following procedures have been establishes by the University

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

    SciTech Connect (OSTI)

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

    2000-04-21T23:59:59.000Z

    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.

  17. Campus Safety Standard Operating Procedure

    E-Print Network [OSTI]

    Miami, University of

    /01/13 PURPOSE To establish policies and procedures for motor vehicle parking and operation on Rosenstiel School of Marine and Atmospheric Science Campus. POLICY All non-commercial vehicles parking on the RSMAS Campus in conflict with this procedure are revoked. 1.0 GENERAL 1.1 Motor vehicles are considered parked when stopped

  18. LOCKOUT/TAGOUT Policy & Procedure

    E-Print Network [OSTI]

    Berdichevsky, Victor

    LOCKOUT/TAGOUT Policy & Procedure Office of Environmental Health and Safety 5425 Woodward, Suite This procedure establishes the Wayne State University requirements for the lockout of energy isolating devices that employee's duties include performing service or maintenance covered under this section. Lockout

  19. STANDARD OPERATING PROCEDURES Site Selection

    E-Print Network [OSTI]

    Fischer, Emily V.

    IMPROVE STANDARD OPERATING PROCEDURES SOP 126 Site Selection Date Last Modified Modified by: 09 References none #12;SOP 126: Site Selection 3 1.0 PURPOSE AND APPLICABILITY This standard operating procedure field conditions, and for ease of operation and maintenance. IMPROVE aerosol samplers are generally

  20. ENERGY MANAGEMENT OPERATIONAL PROCEDURE MANUAL

    E-Print Network [OSTI]

    Harman, Neal.A.

    ENERGY MANAGEMENT OPERATIONAL PROCEDURE MANUAL Swansea University Estates Services Singleton Park Swansea SA2 8PP Tel 01792 295819 Fax 01792 295820 #12;Swansea University Energy Management Operational ......................................................................................11 #12;Swansea University Energy Management Operational Procedural Manual Estates Services April 2008

  1. Fuel Station Procedure Applicability All

    E-Print Network [OSTI]

    Moore, Paul A.

    Fuel Station Procedure Applicability All Last Revised 11/20/12 Procedure Owner Andrew Grant agrant for the purchasing and distribution of fuel for vehicles owned by Bowling Green State University (BGSU). This centralization is important to ensure compliance for BGSU employees who use the centralized fuel station and fuel

  2. TRAITEMENT DES EFFLUENTS WASTE TREATMENT

    E-Print Network [OSTI]

    Boyer, Edmond

    residence time the production of biogas (7l-78 p. 100 CH,) was 237 1 per kg dry matter, i.e. 479 1 of CH to obtain the same amount of biogas four times quicklier. The treatment yield was improved (65 p. 100 COD). The mean production was 4931 biogas/kg degraded COD. It seems to be possible to apply that procedure

  3. Specified assurance level sampling procedure

    SciTech Connect (OSTI)

    Willner, O.

    1980-11-01T23:59:59.000Z

    In the nuclear industry design specifications for certain quality characteristics require that the final product be inspected by a sampling plan which can demonstrate product conformance to stated assurance levels. The Specified Assurance Level (SAL) Sampling Procedure has been developed to permit the direct selection of attribute sampling plans which can meet commonly used assurance levels. The SAL procedure contains sampling plans which yield the minimum sample size at stated assurance levels. The SAL procedure also provides sampling plans with acceptance numbers ranging from 0 to 10, thus, making available to the user a wide choice of plans all designed to comply with a stated assurance level.

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

    SciTech Connect (OSTI)

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

    2013-09-19T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Peters, T.; Fink, S.

    2012-04-24T23:59:59.000Z

    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).

  6. Disability Housing Accommodations Procedures & Guidelines

    E-Print Network [OSTI]

    Heller, Barbara

    Disability Housing Accommodations Procedures & Guidelines In compliance with Section 504 reasonable accommodations to students with disabilities in housing. According to the ADA, a disability to live in IIT's traditional housing arrangements, accommodations are provided. Housing accommodations

  7. Forrestal Security and Safety Procedures

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

    1983-02-02T23:59:59.000Z

    To establish uniform procedures for the security and safety of the Forrestal Building and to inform all personnel of precautionary measures. This directive does not cancel another directive. Canceled by DOE N 251.11.

  8. POSTGRADUATE PROGRAMMES Procedures and Requirements

    E-Print Network [OSTI]

    Jagannatham, Aditya K.

    Engineering, Materials Science, Mechanical Engineering, Nuclear Engineering and Technology and Photonics Statistics), Mechanical Engineering, Nuclear Engineering and Technology, Photonics Science and Engineering(1) POSTGRADUATE PROGRAMMES Procedures and Requirements INDIAN INSTITUTE OF TECHNOLOGY KANPUR

  9. Surface Environmental Surveillance Procedures Manual

    SciTech Connect (OSTI)

    Hanf, RW; Dirkes, RL

    1990-02-01T23:59:59.000Z

    This manual establishes the procedures for the collection of environmental samples and the performance of radiation surveys and other field measurements. Responsibilities are defined for those personnel directly involved in the collection of samples and the performance of field measurements.

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

    SciTech Connect (OSTI)

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

    2013-04-26T23:59:59.000Z

    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.

  11. U.A.C. R315-3: Application and Permit Procedures for Hazardous...

    Open Energy Info (EERE)

    U.A.C. R315-3: Application and Permit Procedures for Hazardous Waste Treatment, Storage, and Disposal Facilities Jump to: navigation, search OpenEI Reference LibraryAdd to library...

  12. Fabrication, qualification and test of high Jc ROEBEL YBCO coated conductor cable for HEP magnets

    SciTech Connect (OSTI)

    Lombardo, V.; Barzi, E.; Turrioni, D.; Zlobin, A.V.; /Fermilab; Long, N.J.; Badcock, R.A.

    2010-08-01T23:59:59.000Z

    The ROEBEL cable concept allows for a high critical current cable assembled using commercially available YBa{sub 2}Cu{sub 3}O{sub 7-{Delta}} coated conductors. this approach to cable design leads to several technological improvements if applied to the manufacture process of next generation low inductance, high current density HTS coils. A reduction in inductance proves to be extremely important when it comes to protection of coils capable of generating fields in the range of 40-50T, such as the ones needed in the last stage of the cooling channel of a muon collider. In this work several aspects are presented including the qualification and minimum requirements for YBa{sub 2}Cu{sub 3}O{sub 7-{Delta}}coated conductor in terms of 2D current density uniformity and the manufacturing process of ROEBEL cables. Test results achieved using a superconducting transformer for critical current measurements in liquid helium are shown, discussed and compared to the performance of a single YBa{sub 2}Cu{sub 3}O{sub 7-{Delta}} coated conductor tape.

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

    SciTech Connect (OSTI)

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

    2011-09-01T23:59:59.000Z

    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).

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

    SciTech Connect (OSTI)

    Peters, T.; Fink, S.

    2011-06-22T23:59:59.000Z

    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).

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

    SciTech Connect (OSTI)

    Unknown

    2002-02-08T23:59:59.000Z

    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.

  16. PROCEDURE Page 1 of 5 Procedure #: 3.1.24

    E-Print Network [OSTI]

    Kemner, Ken

    , administrative costs for collection, and (if still unpaid after 120 days) penalties. In addition, if invoices of materials, or manufacturing methods, processes, or treatments, including minor modifications thereof

  17. Safe Operating Procedure (Revised 1/09)

    E-Print Network [OSTI]

    Farritor, Shane

    protective equipment, agent hazard information, and entry and exit requirements and procedures. Information-4925 · http://ehs.unl.edu #12;Practices and Procedures · Entry and exit procedures and restrictions

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

    SciTech Connect (OSTI)

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

    2010-01-27T23:59:59.000Z

    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.

  19. POLICY GUIDANCE MEMORANDUM #31 - Procedures for Regularizing...

    Energy Savers [EERE]

    1 - Procedures for Regularizing Illegal Appointments POLICY GUIDANCE MEMORANDUM 31 - Procedures for Regularizing Illegal Appointments As part of the Department's ongoing effort to...

  20. Procedures and Instructions | Department of Energy

    Energy Savers [EERE]

    and Instructions Records Management Processes Procedure for Conducting a Records Inventory (PDF) Procedure for Preparing a Records Inventory and Disposition Schedule (RIDS)...

  1. Presidential Permits - Procedures | Department of Energy

    Office of Environmental Management (EM)

    Procedures Presidential Permits - Procedures Executive Order 12038 states that, before a Presidential permit may be issued, the action must be found to be consistent with the...

  2. Authentication Procedures - The Procedures and Integration Working Group

    SciTech Connect (OSTI)

    Kouzes, Richard T.; Bratcher, Leigh; Gosnell, Tom; Langner, Diana; MacArthur, D.; Mihalczo, John T.; Pura, Carolyn; Riedy, Alex; Rexroth, Paul; Scott, Mary; Springarn, Jay

    2001-05-31T23:59:59.000Z

    Authentication is how we establish trust in monitoring systems and measurements to verify compliance with, for example, the storage of nuclear weapons material. Authentication helps assure the monitoring party that accurate and reliable information is provided by any measurement system and that any irregularities are detected. The U.S. is developing its point of view on the procedures for authentication of monitoring systems now planned or contemplated for arms reduction and control applications. The authentication of a system utilizes a set of approaches, including: functional testing using trusted calibration sources, evaluation of documentation, evaluation of software, evaluation of hardware, random selection of hardware and software, tamper-indicating devices, and operational procedures. Authentication of measurement systems should occur throughout their lifecycles, starting with the elements of design, and moving to off-site authentication, on-siste authentication, and continuing with authentication following repair. The most important of these is the initial design of systems. Hardware and software design criteria and procurement decisions can make future authentication relatively straightforward or conversely very difficult. Facility decisions can likewise ease the procedures for authentication since reliable and effective monitoring systems and tampering indicating devices can help provide the assurance needed in the integrity of such items as measurement systems, spare equipment, and reference sources. This paper will summarize the results of the U.S. Authentication Task Force discussion on the role of procedures in authentication.

  3. Procedures

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's Possible forPortsmouth/Paducah47,193.70 Hg Mercury 35 Br BromineProbing the Proton's

  4. BOMB THREAT CHECKLIST Telephone Procedures

    E-Print Network [OSTI]

    Derisi, Joseph

    BOMB THREAT CHECKLIST Telephone Procedures DATE: / / TIME RECEIVED: : AM/PM CONCLUDED: : AM - GIVE NOTE SAYING "CALL UC POLICE - BOMB THREAT" 9-911 IF YOUR PHONE HAS CALLER ID DISPLAY, RECORD NUMBER OF INCOMING CALL __________________________ WRITE DOWN EXACT WORDS OF THE CALLER AND THREAT DON

  5. Software Verification and Validation Procedure

    SciTech Connect (OSTI)

    Olund, Thomas S.

    2008-09-15T23:59:59.000Z

    This Software Verification and Validation procedure provides the action steps for the Tank Waste Information Network System (TWINS) testing process. The primary objective of the testing process is to provide assurance that the software functions as intended, and meets the requirements specified by the client. Verification and validation establish the primary basis for TWINS software product acceptance.

  6. EML Procedures Manual, HASL-300

    SciTech Connect (OSTI)

    Not Available

    1981-09-28T23:59:59.000Z

    Additions and corrections for the EML Procedures Manual, HASL-300, are presented for the following areas: wet/dry collector; ion chamber; field gamma spectrometry; TLD; reactive gas monitoring; cesium; cadmium and lead; carbon dioxide; polynuclear aromatic hydrocarbons; manganese precipitation samples; iron precipitation samples; aluminium precipitation samples; and lead precipitation samples.

  7. Budget Reconciliation Procedures Reference Guide

    E-Print Network [OSTI]

    Shull, Kenneth R.

    Budget Reconciliation Procedures Reference Guide eDev Course Number FMS723 Subject Area Budget Northwestern University #12;Reference Guide Budget Reconciliation Table of Contents Helpful Contacts....................................................................................... 14 723QuickRefGuidev1.4 2 of 14 #12;Reference Guide Budget Reconciliation Helpful Contacts Below

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

    SciTech Connect (OSTI)

    Don Osborne

    2005-06-30T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

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

    2013-08-08T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

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

    1993-05-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    2008-11-10T23:59:59.000Z

    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.

  12. Test procedure for boxed waste assay system

    SciTech Connect (OSTI)

    Wachter, J. [Los Alamos National Lab., NM (United States)

    1994-12-07T23:59:59.000Z

    This document, prepared by Los Alamos National Laboratory`s NMT-4 group, details the test methodology and requirements for Acceptance/Qualification testing of a Boxed Waste Assay System (BWAS) designed and constructed by Pajarito Scientific Corporation. Testing of the BWAS at the Plutonium Facility (TA55) at Los Alamos National Laboratory will be performed to ascertain system adherence to procurement specification requirements. The test program shall include demonstration of conveyor handling capabilities, gamma ray energy analysis, and imaging passive/active neutron accuracy and sensitivity. Integral to these functions is the system`s embedded operating and data reduction software.

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

    SciTech Connect (OSTI)

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

    2012-02-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Pham, Binh T; Einerson, Jeffrey J

    2014-07-01T23:59:59.000Z

    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

  15. E-Print Network 3.0 - arteriovenous fistulae treatment Sample...

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

    OF PROCEDURES INTERNATIONAL CLASSIFICATION OF DISEASES Summary: Excludes: low-dose infusion interleukin-2 (99.28) 00.16 Pressurized treatment of venous bypass graft... conduit...

  16. DOE/OR-1066R5/02-03 5-1 5. LABORATORY PROCEDURES

    E-Print Network [OSTI]

    Pennycook, Steve

    environmental, radiological, mixed-waste, defense, and industrial hygiene programs. The organization's qualifications include American Industrial Hygiene Association (AIHA) accreditation; state of Tennessee Drinking

  17. Qualification of Class 1E static battery charges and inverters for nuclear power generating stations

    SciTech Connect (OSTI)

    Not Available

    1981-01-01T23:59:59.000Z

    This standard describes methods for qualifying static battery chargers and inverters for Class 1E installations in environmentally controlled areas outside containment in nuclear power generating stations. The purpose of this standard is to provide specific procedures to meet the requirements of IEEE Std. 323-1974.

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

    SciTech Connect (OSTI)

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

    2013-02-25T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    None

    1981-04-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    1996-04-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    2013-05-01T23:59:59.000Z

    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.

  2. Advanced Pipe Replacement Procedure for a Defective CRDM Housing Nozzle Enables Continued Normal Operation of a Nuclear Power Plant

    SciTech Connect (OSTI)

    Gilmore, Geoff; Becker, Andrew [Climax Portable Machine Tools, Inc., 2712 East Second Street, Newberg, OR 97132 (United States)

    2006-07-01T23:59:59.000Z

    During the 2003 outage at the Ringhals Nuclear Plant in Sweden, a leak was found in the vicinity of a Control Rod Drive Mechanism (CRDM) housing nozzle at Unit 1. Based on the ALARA principle for radioactive contamination, a unique repair process was developed. The repair system includes utilization of custom, remotely controlled GTAW-robots, a CNC cutting and finishing machine, snake-arm robots and NDE equipment. The success of the repair solution was based on performing the machining and welding operations from the inside of the SCRAM pipe through the CRDM housing since accessibility from the outside was extremely limited. Before the actual pipe replacement procedure was performed, comprehensive training programs were conducted. Training was followed by certification of equipment, staff and procedures during qualification tests in a full scale mock-up of the housing nozzle. Due to the ingenuity of the overall repair solution and training programs, the actual pipe replacement procedure was completed in less than half the anticipated time. As a result of the successful pipe replacement, the nuclear power plant was returned to normal operation. (authors)

  3. Waste segregation procedures and benefits

    SciTech Connect (OSTI)

    Fish, J.D.; Massey, C.D.; Ward, S.J.

    1990-01-01T23:59:59.000Z

    Segregation is a critical first step in handling hazardous and radioactive materials to minimize the generation of regulated wastes. In addition, segregation can significantly reduce the complexity and the total cost of managing waste. Procedures at Sandia National Laboratories, Albuquerque require that wastes be segregated, first, by waste type (acids, solvents, low level radioactive, mixed, classified, etc.). Higher level segregation requirements, currently under development, are aimed at enhancing the possibilities for recovery, recycle and reapplication; reducing waste volumes; reducing waste disposal costs, and facilitating packaging storage, shipping and disposal. 2 tabs.

  4. Segmentation and visualization for cardiac ablation procedures

    E-Print Network [OSTI]

    Depa, Michal

    2011-01-01T23:59:59.000Z

    In this thesis, we present novel medical image analysis methods to improve planning and outcome evaluation of cardiac ablation procedures. Cardiac ablation is a common medical procedure that consists of burning cardiac ...

  5. UNIVERSITY OF ABERDEEN RISK MANAGEMENT POLICY & PROCEDURES

    E-Print Network [OSTI]

    Levi, Ran

    UNIVERSITY OF ABERDEEN RISK MANAGEMENT POLICY & PROCEDURES 1 INTRODUCTION This document sets out the policy and procedures for risk management within the University and replaces earlier documentation. The risk management process is formally integrated with the University's strategic planning process

  6. OLD DOMINION UNIVERSITY University Policies and Procedures

    E-Print Network [OSTI]

    AND ADMINISTRATOR RECRUITMENT FUNDING PROCEDURE Statement: University Recruitment Budget (1) The university6010 - 1 OLD DOMINION UNIVERSITY University Policies and Procedures 6010 - FACULTY maintains a central budget, called the University Recruitment Budget, for the support of essential

  7. UCSD Implementing Procedures 12/Nondiscrimination in Employment

    E-Print Network [OSTI]

    Russell, Lynn

    UCSD Implementing Procedures (HR-S-1) 12/Nondiscrimination in Employment 12/Nondiscrimination in Employment B. UC PPSM 14/Affirmative Action C. UCSD Implementing Procedures) issues an annual statement reaffirming the systemwide Nondiscrimination in Employment Policy. All

  8. POLICY: A:VPFA # / Purchasing Policy PROCEDURES

    E-Print Network [OSTI]

    Martin, Jeff

    POLICY: A:VPFA # / Purchasing Policy PROCEDURES: APPENDIX: Approved: April 1, 2013 Revised: Cross References: Purchasing Policy Capital Projects and Renovations Policy Conflict of Interest Policy Sustainability Policy Green Procurement Policy 1 of 9 PROCEDURES: Purchasing Policy AUTHORITY: University

  9. 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

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

    SciTech Connect (OSTI)

    Sun, K. X.

    2011-05-31T23:59:59.000Z

    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.

  11. 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]

    Brest, Université de

    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

  12. Effect of Music Therapy with Emotional-Approach Coping on Pre-Procedural Anxiety in Cardiac Catheterization

    E-Print Network [OSTI]

    Ghetti, Claire

    2011-06-27T23:59:59.000Z

    of invasive procedures are used for diagnosis and treatment of CHD including bypass surgeries, percutaneous coronary interventions (PCI), diagnostic cardiac catheterizations, and implantation of defibrillators and pacemakers. Cardiac catheterization...

  13. Safe Operating Procedure (Revised 6/10)

    E-Print Network [OSTI]

    Farritor, Shane

    or other responsible person1-2 The procedures required for Entry1-2 The procedures required for Exit2 Date provisions for entry into the laboratory are required1 ; or (c) the work space is an HIV and HBV Research or other responsible person (required for BSL-2 and higher)1-3 The procedures required for Entry (required

  14. STANDARD OPERATING PROCEDURES Annual Site Maintenance

    E-Print Network [OSTI]

    Fischer, Emily V.

    IMPROVE STANDARD OPERATING PROCEDURES SOP 226 Annual Site Maintenance Date Last Modified Modified This standard operating procedure (SOP) describes the procedures for annual maintenance of equipment Sampler Operation Manual #12;SOP 226: Annual Site Maintenance 3 1.0 PURPOSE AND APPLICABILITY

  15. PHYSICAL PLANT OPERATING POLICY AND PROCEDURE

    E-Print Network [OSTI]

    Gelfond, Michael

    PHYSICAL PLANT OPERATING POLICY AND PROCEDURE PP/OP 04.05: Development of Standard Labor Charge and Procedure (PP/OP) is to establish procedures for the development of a standard labor charge rate used when-600) ­ Account used to fund all maintenance and operation expenses for Custodial Services #12;June 7, 2010 Page 2

  16. Environmental Measurements Laboratory (EML) procedures manual

    SciTech Connect (OSTI)

    Chieco, N.A.; Bogen, D.C.; Knutson, E.O. (eds.)

    1990-11-01T23:59:59.000Z

    Volume 1 of this manual documents the procedures and existing technology that are currently used by the Environmental Measurements Laboratory. A section devoted to quality assurance has been included. These procedures have been updated and revised and new procedures have been added. They include: sampling; radiation measurements; analytical chemistry; radionuclide data; special facilities; and specifications. 228 refs., 62 figs., 37 tabs. (FL)

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

    SciTech Connect (OSTI)

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

    2012-05-11T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    David Petti

    2014-06-01T23:59:59.000Z

    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.

  19. DESIGN OF THE HANFORD MULTI CANISTER OVERPACK (MCO) & DEVELOPMENT & QUALIFICATION OF THE CLOSURE WELDING PROCESS

    SciTech Connect (OSTI)

    CANNELL, G. R.

    2004-04-30T23:59:59.000Z

    Processing more than 2,100 metric tons of metallic uranium spent nuclear fuel (SNF) into large stainless steel containers called Multi-Canister Overpacks (MCOs) is one of the top priorities for the Department of Energy (DOE) at the Hanford Site, located in southeastern Washington state. The MCOs will be temporarily stored on site and eventually shipped to the federal geologic repository for long-term storage. MCOs are constructed and ''N''stamped in accordance with the requirements of the American Society of Mechanical Engineers (ASME) Section III, Division 1, Class 1 Components. Final closure welding poses a challenge after the fuel is loaded. Performing required examination and testing activities (volumetric examination and hydrostatic leak testing) can be difficult, if not impractical. An ASME Code Case N-595-3, was written specifically to allow code stamping by addressing such closures and providing alternative rules. MCOs are the first SNF canisters within the DOE complex to successfully use this code case for receiving ASME stamps. This paper discusses the design of the MCO, application of the N-595-3 code case, and development and qualification of the final welded closure. The MCO design considers internal pressure and handling loads, as well as processing and interim storage activities. The MCO functions as the primary or innermost containment as part of an overall transportation package so the design also considered interface features with secondary and transport containers. The MCO, approximately 2 feet in diameter and nearly 14 feet tall, is constructed primarily of Type 304/304L stainless steel and the final pressure boundary is of all-welded construction. The closure-weld is made with the Gas Tungsten Arc Welding (GTAW) process, using an automatic, machine-welding mode. Examination and testing of the closure includes the N-595-3 specified requirements-progressive Liquid Penetrant testing (PT) and final helium leak testing. At completion of the closure, the MCO is ''N'' stamped as a 450 pounds per square inch (design pressure) vessel. To ensure the process consistently achieves the required weld penetration, a series of developmental tests was performed to identify an optimum and robust set of welding parameters. Testing included test welds made on plate mockups and then actual MCO mockups. With the primary welding parameters (welding current and travel speed) established, a simple two-factor, two-level, factorial experiment with replication at high and low heat input conditions was conducted. Evaluation of the results included weld photomicrographs, which helped establish process range limits for these parameters broad enough to cover typical equipment and measurement variations and provide additional operating margin. To date, over 316 MCOs have been loaded, dried, and transported to the Canister Storage Building (CSB), where the welding is done. Of those, 161 MCOs have received final welded closure and ''N'' stamps. All cover cap final closure welds have met specified requirements without incident.

  20. HUMAN RELIABILITY ANALYSIS FOR COMPUTERIZED PROCEDURES

    SciTech Connect (OSTI)

    Ronald L. Boring; David I. Gertman; Katya Le Blanc

    2011-09-01T23:59:59.000Z

    This paper provides a characterization of human reliability analysis (HRA) issues for computerized procedures in nuclear power plant control rooms. It is beyond the scope of this paper to propose a new HRA approach or to recommend specific methods or refinements to those methods. Rather, this paper provides a review of HRA as applied to traditional paper-based procedures, followed by a discussion of what specific factors should additionally be considered in HRAs for computerized procedures. Performance shaping factors and failure modes unique to computerized procedures are highlighted. Since there is no definitive guide to HRA for paper-based procedures, this paper also serves to clarify the existing guidance on paper-based procedures before delving into the unique aspects of computerized procedures.

  1. Radiological Work Planning and Procedures

    E-Print Network [OSTI]

    Kurtz, J E

    2000-01-01T23:59:59.000Z

    Each facility is tasked with maintaining personnel radiation exposure as low as reasonably achievable (ALARA). A continued effort is required to meet this goal by developing and implementing improvements to technical work documents (TWDs) and work performance. A review of selected TWDs from most facilities shows there is a need to incorporate more radiological control requirements into the TWD. The Radioactive Work Permit (RWP) provides a mechanism to place some of the requirements but does not provide all the information needed by the worker as he/she is accomplishing the steps of the TWD. Requiring the engineers, planners and procedure writers to put the radiological control requirements in the work steps would be very easy if all personnel had a strong background in radiological work planning and radiological controls. Unfortunately, many of these personnel do not have the background necessary to include these requirements without assistance by the Radiological Control organization at each facility. In add...

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

    SciTech Connect (OSTI)

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

    2011-07-08T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    2013-03-18T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    1982-09-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

    Michael L. Abbott; Binh T. Pham

    2012-06-01T23:59:59.000Z

    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.

  6. Safe Operating Procedure SAFETY AUDIT GUIDELINES FOR BIOSAFETY LEVEL 2

    E-Print Network [OSTI]

    Farritor, Shane

    analysis, unique facility/equipment attributes, etc. The audit checklist for chemical laboratories is also to substantiate current medical qualification/testing of all persons listed in the protocol (as applicable). Facility Design and Equipment Inspection Lab doors are operable and kept closed while work is in progress

  7. Attachment 1: Green Lease Policies and Procedures for Lease Acquisitio...

    Office of Environmental Management (EM)

    1: Green Lease Policies and Procedures for Lease Acquisition Attachment 1: Green Lease Policies and Procedures for Lease Acquisition Green Lease Policies and Procedures for Lease...

  8. Radiological Work Planning and Procedure

    SciTech Connect (OSTI)

    KURTZ, J.E.

    2000-01-01T23:59:59.000Z

    Each facility is tasked with maintaining personnel radiation exposure as low as reasonably achievable (ALARA). A continued effort is required to meet this goal by developing and implementing improvements to technical work documents (TWDs) and work performance. A review of selected TWDs from most facilities shows there is a need to incorporate more radiological control requirements into the TWD. The Radioactive Work Permit (RWP) provides a mechanism to place some of the requirements but does not provide all the information needed by the worker as he/she is accomplishing the steps of the TWD. Requiring the engineers, planners and procedure writers to put the radiological control requirements in the work steps would be very easy if all personnel had a strong background in radiological work planning and radiological controls. Unfortunately, many of these personnel do not have the background necessary to include these requirements without assistance by the Radiological Control organization at each facility. In addition, there seems to be confusion as to what should be and what should not be included in the TWD.

  9. A general design for energy test procedures

    SciTech Connect (OSTI)

    Meier, Alan

    2000-06-15T23:59:59.000Z

    Appliances are increasingly controlled by microprocessors. Unfortunately, energy test procedures have not been modified to capture the positive and negative contributions of the microprocessor to the appliance's energy use. A new test procedure is described which captures both the mechanical and logical features present in many new appliances. We developed an energy test procedure for refrigerators that incorporates most aspects of the proposed new approach. Some of the strengths and weaknesses of the new test are described.

  10. Radiation Safety Policy and Procedures Committee

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

    RSPPC Meeting Minutes APS only Radiation Safety Policy and Procedures Committee Charter 1. Purpose The committee reviews functional changes to the Access Control Interlock System...

  11. J1634 SAE BEV Test Procedures

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

    J1634 SAE BEV Test Procedures 2010 DOE Hydrogen Program and Vehicle Technologies Annual Merit Review June 09, 2010 Michael Duoba Argonne National Laboratory Sponsored by Lee Slezak...

  12. Slimhole Handbook- Procedures and Recommendations for Slimhole...

    Open Energy Info (EERE)

    to library Report: Slimhole Handbook- Procedures and Recommendations for Slimhole Drilling and Testing in Geothermal Exploration Abstract No abstract prepared. Authors Jim...

  13. Slimhole Handbook- Procedures And Recommendations For Slimhole...

    Open Energy Info (EERE)

    Handbook- Procedures And Recommendations For Slimhole Drilling And Testing In Geothermal Exploration Jump to: navigation, search OpenEI Reference LibraryAdd to library Report:...

  14. RADIATION SAFETY MANUAL POLICIES AND PROCEDURES

    E-Print Network [OSTI]

    Zhang, Yuanlin

    RADIATION SAFETY MANUAL POLICIES AND PROCEDURES FOR RADIATION PROTECTION AT TEXAS TECH UNIVERSITY................................................................................................................I-1 B. Radiation Protection Program...............................................................................I-3 D. Radiation Safety Management

  15. Hazardous Material Packaging for Transport - Administrative Procedures

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

    1986-09-30T23:59:59.000Z

    To establ1sh administrative procedures for the certification and use of radioactive and other hazardous materials packaging by the Department of Energy (DOE).

  16. Hybrid LP/SDP Bounding Procedure

    E-Print Network [OSTI]

    2012-10-24T23:59:59.000Z

    on sophisticated Branch and Cut (BC) algorithms based on a smart implicit enumeration of the branching tree. The bounding procedure typically makes use.

  17. Verification and Validation of Facilities Procedures Assessment...

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

    Verification and Validation of Facilities Procedures Assessment Plan NNSANevada Site Office Independent Oversight Division Performance Objective: The purpose of this assessment is...

  18. Petroleum Pipeline Eminent Domain Permit Procedures (Georgia)

    Broader source: Energy.gov [DOE]

    The Petroleum Pipeline Eminent Domain Permit Procedures serve to protect Georgia's natural and environmental resources by requiring permits be issued by the Director of the Environmental Protection...

  19. Waimairi Clinic Policies, Procedures and Protocols

    E-Print Network [OSTI]

    Hickman, Mark

    Waimairi Clinic Policies, Procedures and Protocols July 2010 College of Education #12;Table The Facilities............................................................................2 Booking a Clinic room ............................................................................................... 3 Access to Clinics.......................................................................3

  20. Additional Guidance Regarding Application of Current Procedures...

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

    Additional Guidance Regarding Application of Current Procedures for Testing Energy Consumption of Clothes Washers with Warm Rinse Cycles, Issued: June 30, 2010. Draft of DOE...

  1. Pollutant Assessments Group Procedures Manual: Volume 1, Administrative and support procedures

    SciTech Connect (OSTI)

    Not Available

    1992-03-01T23:59:59.000Z

    This manual describes procedures currently in use by the Pollutant Assessments Group. The manual is divided into two volumes: Volume 1 includes administrative and support procedures, and Volume 2 includes technical procedures. These procedures are revised in an ongoing process to incorporate new developments in hazardous waste assessment technology and changes in administrative policy. Format inconsistencies will be corrected in subsequent revisions of individual procedures. The purpose of the Pollutant Assessments Groups Procedures Manual is to provide a standardized set of procedures documenting in an auditable manner the activities performed by the Pollutant Assessments Group (PAG) of the Health and Safety Research Division (HASRD) of the Environmental Measurements and Applications Section (EMAS) at Oak Ridge National Laboratory (ORNL). The Procedures Manual ensures that the organizational, administrative, and technical activities of PAG conform properly to protocol outlined by funding organizations. This manual also ensures that the techniques and procedures used by PAG and other contractor personnel meet the requirements of applicable governmental, scientific, and industrial standards. The Procedures Manual is sufficiently comprehensive for use by PAG and contractor personnel in the planning, performance, and reporting of project activities and measurements. The Procedures Manual provides procedures for conducting field measurements and includes program planning, equipment operation, and quality assurance elements. Successive revisions of this manual will be archived in the PAG Document Control Department to facilitate tracking of the development of specific procedures.

  2. Optimization of proteomic sample preparation procedures for comprehens...

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

    procedures for comprehensive protein characterization of pathogenic systems. Optimization of proteomic sample preparation procedures for comprehensive protein...

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

    SciTech Connect (OSTI)

    D. P. Blanchard; R. W. Youngblood

    2014-06-01T23:59:59.000Z

    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.

  4. Qualification testing and full-scale demonstration of titanium-treated zeolite for sludge wash processing

    SciTech Connect (OSTI)

    Dalton, W.J.

    1997-06-30T23:59:59.000Z

    Titanium-treated zeolite is a new ion-exchange material that is a variation of UOP (formerly Union Carbide) IONSIV IE-96 zeolite (IE-96) that has been treated with an aqueous titanium solution in a proprietary process. IE-96 zeolite, without the titanium treatment, has been used since 1988 in the West Valley Demonstration Project`s (WVDP) Supernatant Treatment System (STS) ion-exchange columns to remove Cs-137 from the liquid supernatant solution. The titanium-treated zeolite (TIE-96) was developed by Battelle-Pacific Northwest Laboratory (PNL). Following successful lab-scale testing of the PNL-prepared TIE-96, UOP was selected as a commercial supplier of the TIE-96 zeolite. Extensive laboratory tests conducted by both the WVDP and PNL indicate that the TIE-96 will successfully remove comparable quantities of Cs-137 from Tank 8D-2 high-level radioactive liquid as was done previously with IE-96. In addition to removing Cs-137, TIE-96 also removes trace quantities of Pu, as well as Sr-90, from the liquid being processed over a wide range of operating conditions: temperature, pH, and dilution. The exact mechanism responsible for the Pu removal is not fully understood. However, the Pu that is removed by the TIE-96 remains on the ion-exchange column under anticipated sludge wash processing conditions. From May 1988 to November 1990, the WVDP processed 560,000 gallons of liquid high-level radioactive supernatant waste stored in Tank 8D-2. Supernatant is an aqueous salt solution comprised primarily of soluble sodium salts. The second stage of the high-level waste treatment process began November 1991 with the initiation of sludge washing. Sludge washing involves the mixing of Tank 8D-2 contents, both sludge and liquid, to dissolve the sulfate salts present in the sludge. Two sludge washes were required to remove sulfates from the sludge.

  5. CUNY EXPORT CONTROL PROCEDURES 11. Procurement

    E-Print Network [OSTI]

    Rosen, Jay

    CUNY EXPORT CONTROL PROCEDURES 11. Procurement This section addresses the identification of export to normal outbound export controls. Hence, it is CUNY's procedure to require vendors of laboratory to the laboratory user or administrator and the Export Control Administrator for the College. The Export Control

  6. 9 TOWARD A MODEL OF ACQUIRING PROCEDURES

    E-Print Network [OSTI]

    Kieras, David E.

    with procedural text in daily life is that people often do not read it when they should. Although many people called reading to do, where people read in order to carry out some task. The Need for Research on procedural text and also shows the weakness of our current understanding. Do People Read Instructions? One

  7. A diagnostic procedure for multivariate quality control

    E-Print Network [OSTI]

    Keserla, Adhinarayan A.

    1993-01-01T23:59:59.000Z

    . The proposed diagnostic procedure is triggered by off-target signals from the multivariate control chart. The performance of the procedure are investigate in conjunction with the two control charts, the X2 chart and the MC1 chart. Two performance measures...

  8. Procedures and Standards for Residential Ventilation System

    E-Print Network [OSTI]

    1 Procedures and Standards for Residential Ventilation System Commissioning: An Annotated and by the California Energy Commission under Pier Contract 500-08-061. Key terms: residential, ventilation.C. and C.P. Wray. 2013. Procedures and Standards for Residential Ventilation System Commissioning

  9. Safe Operating Procedure (Created 5/11)

    E-Print Network [OSTI]

    Farritor, Shane

    ://ehs.unl.edu (5/11) LOCKOUT/TAGOUT FOR MACHINES & EQUIPMENT: WRITTEN PROCEDURES during maintenance and repair operations. In these situations, a lockout/tagout (LO/TO) program must/TO procedures, as well as other program requirements. See EHS SOP, Lockout/Tagout for Machines & Equipment

  10. W-087 Acceptance test procedure. Revision 1

    SciTech Connect (OSTI)

    Joshi, A.W.

    1997-06-10T23:59:59.000Z

    This Acceptance Test Procedure/Operational Test Procedure (ATP/OTP) has been prepared to demonstrate that the Electrical/Instrumentation and Mechanical systems function as required by project criteria and to verify proper operation of the integrated system including the interlocks.

  11. CONTROL VALVE TESTING PROCEDURES AND EQUATIONS

    E-Print Network [OSTI]

    Rahmeyer, William J.

    APPENDIX A CONTROL VALVE TESTING PROCEDURES AND EQUATIONS FOR LIQUID FLOWS #12;APPENDIX A CONTROL VALVE TESTING PROCEDURES AND EQUATIONS FOR LIQUID FLOWS 2 Cv Q P Sg net gpm net = / Cv = Q P / Sg 75 is used to relate the pressure loss of a valve to the discharge of the valve at a given valve opening

  12. UC Davis Policy and Procedure Manual Introduction

    E-Print Network [OSTI]

    California at Davis, University of

    UC Davis Policy and Procedure Manual Introduction Development and Management of Campus Sections Exhibit B, Policy Development Best Practices Exhibit C, New Policy Development Plan Exhibit D of the Chancellor and Provost Source Document: N/A 1 of 5 Exhibit A, Structure for Policy and Procedure Manual

  13. Safe Operating Procedure (Reviewed 7/09)

    E-Print Network [OSTI]

    Farritor, Shane

    procedures for disposal of hazardous and/or radioactive wastes are to be followed. P-33 waste shouldSafe Operating Procedure (Reviewed 7/09) SAFETY PROTOCOL: P-33://ehs.unl.edu/) Use of radioactive materials requires a safety protocol be submitted to the UNL Radiation Safety

  14. Safe Operating Procedure (Reviewed 7/09)

    E-Print Network [OSTI]

    Farritor, Shane

    mCi. Waste Disposal EHS procedures for disposal of hazardous and/or radioactive wastesSafe Operating Procedure (Reviewed 7/09) SAFETY PROTOCOL: H-3://ehs.unl.edu/) Use of radioactive materials requires a safety protocol be submitted to the UNL Radiation Safety

  15. Safe Operating Procedure (Reviewed 7/09)

    E-Print Network [OSTI]

    Farritor, Shane

    procedures for disposal of hazardous and/or radioactive wastes are to be followed. Cr-51 waste shouldSafe Operating Procedure (Reviewed 7/09) SAFETY PROTOCOL: Cr-51://ehs.unl.edu/) Use of radioactive materials requires a safety protocol be submitted to the UNL Radiation Safety

  16. Safe Operating Procedure (Reviewed 7/09)

    E-Print Network [OSTI]

    Farritor, Shane

    through ingestion is 0.6 mCi. Waste Disposal EHS procedures for disposal of hazardous and/or radioactiveSafe Operating Procedure (Reviewed 7/09) SAFETY PROTOCOL: P-32://ehs.unl.edu/) Use of radioactive materials requires a safety protocol be submitted to the UNL Radiation Safety

  17. Safe Operating Procedure (Revised 9/10)

    E-Print Network [OSTI]

    Farritor, Shane

    ingestion is 0.04 mCi. Waste Disposal EHS procedures for disposal of hazardous and/or radioactive wastesSafe Operating Procedure (Revised 9/10) SAFETY PROTOCOL: I-125://ehs.unl.edu/) Use of radioactive materials requires a safety protocol be submitted to the UNL Radiation Safety

  18. Safe Operating Procedure (Reviewed 7/09)

    E-Print Network [OSTI]

    Farritor, Shane

    ingestion is 9.0 mCi. Waste Disposal EHS procedures for disposal of hazardous and/or radioactive wastesSafe Operating Procedure (Reviewed 7/09) SAFETY PROTOCOL: Fe-55://ehs.unl.edu/) Use of radioactive materials requires a safety protocol be submitted to the UNL Radiation Safety

  19. Safe Operating Procedure (Reviewed 7/09)

    E-Print Network [OSTI]

    Farritor, Shane

    ingestion is 6 mCi. Waste Disposal EHS procedures for disposal of hazardous and/or radioactive wastesSafe Operating Procedure (Reviewed 7/09) SAFETY PROTOCOL: S-35://ehs.unl.edu/) Use of radioactive materials requires a safety protocol be submitted to the UNL Radiation Safety

  20. Safe Operating Procedure (Reviewed 7/09)

    E-Print Network [OSTI]

    Farritor, Shane

    .4 mCi. Waste Disposal EHS procedures for disposal of hazardous and/or radioactive wastesSafe Operating Procedure (Reviewed 7/09) SAFETY PROTOCOL: Na-22://ehs.unl.edu/) Use of radioactive materials requires a safety protocol be submitted to the UNL Radiation Safety

  1. Safe Operating Procedure SAFETY PROTOCOL: Rb-86

    E-Print Network [OSTI]

    Farritor, Shane

    of hazardous and/or radioactive wastes are to be followed. Rb- 86 waste should be segregated from all otherSafe Operating Procedure (2/10) SAFETY PROTOCOL: Rb-86 this safety protocol or submit an alternative and equivalent procedure that you develop to meet your unique

  2. Safe Operating Procedure (Reviewed 7/09)

    E-Print Network [OSTI]

    Farritor, Shane

    through ingestion is 10 mCi. Waste Disposal EHS procedures for disposal of hazardous and/or radioactiveSafe Operating Procedure (Reviewed 7/09) SAFETY PROTOCOL: Se-75://ehs.unl.edu/) Use of radioactive materials requires a safety protocol be submitted to the UNL Radiation Safety

  3. Safe Operating Procedure (Reviewed 7/09)

    E-Print Network [OSTI]

    Farritor, Shane

    of intake through ingestion is 0.8 mCi. Waste Disposal EHS procedures for disposal of hazardous andSafe Operating Procedure (Reviewed 7/09) SAFETY PROTOCOL: Fe-59://ehs.unl.edu/) Use of radioactive materials requires a safety protocol be submitted to the UNL Radiation Safety

  4. Academic Policies and Procedures Graduate Programs

    E-Print Network [OSTI]

    Jiang, Huiqiang

    and Graduation Committee. 3. The academic advisor selects three research articles in the student's researchAcademic Policies and Procedures Graduate Programs Policy No. 230 Page 1 Policy No. 230 UNIVERSITY OF PITTSBURGH SCHOOL OF NURSING ACADEMIC POLICIES AND PROCEDURES FOR THE GRADUATE PROGRAM TITLE OF POLICY

  5. PUBLIC INTEREST DISCLOSURE (PID) POLICY AND PROCEDURES

    E-Print Network [OSTI]

    Greenslade, Diana

    i PUBLIC INTEREST DISCLOSURE (PID) POLICY AND PROCEDURES #12;PUBLIC INTEREST DISCLOSURE POLICY a disclosure under the PID Act 7 5.2. How to make a disclosure under the PID Act 7 6. PROCEDURES FOR AUTHORISED OFFICERS 9 7.1. Authorised Officer must provide information about the PID Act 9 7.2. Receiving

  6. ADMINISTRATION AND FINANCE POLICIES AND PROCEDURES

    E-Print Network [OSTI]

    Rusu, Adrian

    ADMINISTRATION AND FINANCE POLICIES AND PROCEDURES Chapter 1 POLICY DEVELOPMENT & IMPLEMENTATION................................................................................. 3 #12;ADMINISTRATION AND FINANCE POLICIES AND PROCEDURES Chapter 1 POLICY DEVELOPMENT & IMPLEMENTATION Revision Date: 1/26/10 1.01 PURPOSE AND USE OF THE MANUAL This Administration and Finance Policies

  7. PLASMAQUEST STANDARD OPERATING PROCEDURE CORAL Name: Plasmaquest

    E-Print Network [OSTI]

    Reif, Rafael

    PLASMAQUEST STANDARD OPERATING PROCEDURE CORAL Name: Plasmaquest Model Number: 145 Location: TRL. PROCEDURE: Check reservations in CORAL to insure that you reserved the correct machine in the correct, if this is the case. `Engage' the machine in CORAL for the equipment that you are about to use; use this command

  8. Policy Procedure Administrative Directive Policy No.

    E-Print Network [OSTI]

    Northern British Columbia, University of

    Policy ­ Procedure ­ Administrative Directive Title: Policy No.: Effective Date or Date of Last President See also: Related Policies, Procedures and Agreements: Relevant Legislation and Regulations: Background and Purpose: CLEAR DATA #12;Policy *A University Policy is a principle-based statement with broad

  9. Vehicle Maintenance Procedure Outline the procedure for vehicle maintenance at University of Michigan (U-M).

    E-Print Network [OSTI]

    Kirschner, Denise

    Vehicle Maintenance Procedure Objective Outline the procedure for vehicle maintenance at University of Michigan (U-M). Procedure 1. Your U-M vehicle has a mechanical and/or safety issue. 2. Contact Garage of the vehicle or if needed, have the vehicle towed to the maintenance facility. 4. If a loaner is needed while

  10. Qualification of large diameter duplex stainless steel girth welds intended for low temperature service

    SciTech Connect (OSTI)

    Prosser, K.; Robinson, A.G.; Rogers, P.F.

    1996-12-31T23:59:59.000Z

    British Gas recently had a requirement to fabricate some UNS31803 duplex stainless steel pipework for an offshore topsides process plant. The pipework had a maximum diameter of 600mm, with a corresponding wall thickness of 18mm, and it was designed to operate at a minimum temperature of {minus}40 C. There is a lack of published toughness data for girth welds in duplex stainless steel at this thickness and minimum design temperature. Additionally, toughness requirements for girth welds in current pipework and pressure vessel codes are based on experience with carbon steels. As a result, a program of work has been carried out to study the Charpy, CTOD and wide plate toughness of girth welds in 22%Cr duplex stainless steel pipework. The welds were produced using a typical gas tungsten arc/gas metal arc pipework fabrication procedure. In addition, non-destructive evaluation trials have been carried out on a deliberately defective weld using radiography and ultrasonics. It was demonstrated that double wall single image {gamma}-radiography, single wall single image and panoramic X-radiography, and conventional shear wave ultrasonics were all able to detect planar root defects varying from 3 to 7mm in depth. There was good agreement between the sizes recorded by ultrasonics and those measured from macrosections. Small scale mechanical tests demonstrated that welds with overmatching tensile properties, and low temperature toughness properties which were acceptable to specification, could be produced. Wide plate tests demonstrated that defect size calculations from BS PD7493 were conservative.

  11. Human Resources Procedures Manual 16 January 2014 Note these procedures are subject to ongoing review. If you find a procedure which requires updating please notify a member

    E-Print Network [OSTI]

    Liley, David

    Page 1 Human Resources Procedures Manual 16 January 2014 Note these procedures are subject team. Human Resources Procedures Manual Contents Section One: Recruitment and Appointment - Recruitment Management - Public Holidays - Industrial Action - Absence on official business - Academic staff additional

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

    SciTech Connect (OSTI)

    Binh T. Pham

    2014-02-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    2013-05-31T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Molvik, A W; Simonen, T C

    2009-07-17T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    1996-04-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    S. Blaine Grover; David A. Petti

    2007-09-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    CANNELL, G.R.

    2006-09-11T23:59:59.000Z

    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.

  18. Digial Technology Qualification Task 2 - Suitability of Digital Alternatives to Analog Sensors and Actuators

    SciTech Connect (OSTI)

    Ted Quinn; Jerry Mauck

    2012-09-01T23:59:59.000Z

    The next generation reactors in the U.S. are an opportunity for vendors to build new reactor technology with advanced Instrumentation and Control Systems (control rooms, DCS, etc.). The advances made in the development of many current generation operating reactors in other parts of the world are being used in the design and construction of new plants. These new plants are expected to have fully integrated digital control rooms, computerized procedures, integrated surveillance testing with on-line monitoring and a major effort toward improving the O&M and fault survivability of the overall systems. In addition the designs are also incorporating major improvements in the man-machine interface based on lessons learned in nuclear and other industries. The above relates primarily to the scope of supply in instrumentation and control systems addressed by Chapter 7 of the Standard Review Plan (SRP) NUREG-0800 (Reference 9.5), and the associated Balance of Plant (BOP) I&C systems. This does not relate directly to the actuator and motor, breaker, initiation circuitry, valve position, etc. which is the subject of this report and normally outside of the traditional Distributed Control System (DCS), for both safety and non-safety systems. The recommendations presented in this report will be used as input to I&C research programming for the implementation of lessons learned during the early phases of new build both for large light water reactors (LWR) and also small modular reactors (SMR). This report is intended to support current research plans and provide user (vendor, owner-operator) input to the optimization of these research plans.

  19. Health Code Number (HCN) Development Procedure

    SciTech Connect (OSTI)

    Petrocchi, Rocky; Craig, Douglas K.; Bond, Jayne-Anne; Trott, Donna M.; Yu, Xiao-Ying

    2013-09-01T23:59:59.000Z

    This report provides the detailed description of health code numbers (HCNs) and the procedure of how each HCN is assigned. It contains many guidelines and rationales of HCNs. HCNs are used in the chemical mixture methodology (CMM), a method recommended by the department of energy (DOE) for assessing health effects as a result of exposures to airborne aerosols in an emergency. The procedure is a useful tool for proficient HCN code developers. Intense training and quality assurance with qualified HCN developers are required before an individual comprehends the procedure to develop HCNs for DOE.

  20. Athletic Training Admissions Procedures Truman State University

    E-Print Network [OSTI]

    Gering, Jon C.

    Athletic Training Admissions Procedures Truman State University Admission to the athletic training major is competitive and selective. Students interested in majoring in athletic training must complete Athletic Training as their major area of study on the University's application for admission

  1. RECYCLING AND GENERAL WASTE MANAGEMENT OPERATIONAL PROCEDURE

    E-Print Network [OSTI]

    Harman, Neal.A.

    RECYCLING AND GENERAL WASTE MANAGEMENT OPERATIONAL PROCEDURE Swansea University Estates Services.6.1/1 Recycling & General Waste Management Department: Estates & Facilities Management Site: Swansea University recycling and waste management facilities in Swansea university To ensure that Waste Management Objectives

  2. VEHICLE OPERATING PROCEDURES DEPARTMENT OF BIOLOGICAL SCIENCE

    E-Print Network [OSTI]

    Ronquist, Fredrik

    VEHICLE OPERATING PROCEDURES DEPARTMENT OF BIOLOGICAL SCIENCE GENERAL INFORMATION Vehicles resposniblity and disciplinary action. Vehicles may be used by faculty or staff from other departments complete the vehicle usage agreement form certifying that they have a valid driver's license

  3. Financial Policy and Procedures for Reimbursable Work

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

    1988-08-15T23:59:59.000Z

    The directive establishes Department-wide financial policy and procedural guidance applicable to performing reimbursable work for other Federal agencies and with non-Federal Government entities, including foreign and commercial entities, State, and political subdivisions.

  4. DEPARTMENT OF ENERGY PROCEDURES FOR INTELLIGENCE ACTIVITIES

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

    that they have reason to be1 ieve may be illegal or contrary to Executive order, Presidential directive, o r appl i cab1 e DOE pol icy, incl udi ng these Procedures. Such...

  5. Digital Publishing Procedures Category: Information Management

    E-Print Network [OSTI]

    (WA) Policy Manager Vice President Corporate Relations and Development Contact Director, Digital Media1 Digital Publishing Procedures Category: Information Management 1. LEGISLATION a framework for the publishing of the University's digital communications, including but not limited to all

  6. Practical Procedures for Auditing Industrial Boiler Plants

    E-Print Network [OSTI]

    O'Neil, J. P.

    1980-01-01T23:59:59.000Z

    Industrial boiler plants are an area of opportunity in virtually every industry to save energy and reduce costs by using relatively simple, inexpensive auditing procedures. An energy audit consists of inspection, measurement, analysis...

  7. Control Tower Procedures Nolan, Chap 6

    E-Print Network [OSTI]

    1 1 Control Tower Procedures Nolan, Chap 6 2 Control Towers · Responsibilities: 1. Ensure Towers · VFR Towers ­ NOT delegated separation responsibility · Except initial departure traffic ­ ARTCC separates IFR traffic · Non-radar-approach control towers ­ Delegated IFR separation responsibility

  8. Roof Coating Procedures and Their Productivity Gains 

    E-Print Network [OSTI]

    Bonaby, J.; Schaub, D.

    2006-01-01T23:59:59.000Z

    Roof Coating Procedures and their Productivity Gains John Bonaby and Dr. Diane Schaub, University of Florida As building envelope improvements are realized in organizations as ways to insulate businesses from high energy costs, the relative... benefit of the installation of different roof coating technologies and comparable application procedures of these technologies are ambiguous. The focal point of this research is to determine the effective correlation between various commercially...

  9. Procedures for sampling radium-contaminated soils

    SciTech Connect (OSTI)

    Fleischhauer, H.L.

    1985-10-01T23:59:59.000Z

    Two procedures for sampling the surface layer (0 to 15 centimeters) of radium-contaminated soil are recommended for use in remedial action projects. Both procedures adhere to the philosophy that soil samples should have constant geometry and constant volume in order to ensure uniformity. In the first procedure, a ''cookie cutter'' fashioned from pipe or steel plate, is driven to the desired depth by means of a slide hammer, and the sample extracted as a core or plug. The second procedure requires use of a template to outline the sampling area, from which the sample is obtained using a trowel or spoon. Sampling to the desired depth must then be performed incrementally. Selection of one procedure over the other is governed primarily by soil conditions, the cookie cutter being effective in nongravelly soils, and the template procedure appropriate for use in both gravelly and nongravelly soils. In any event, a minimum sample volume of 1000 cubic centimeters is recommended. The step-by-step procedures are accompanied by a description of the minimum requirements for sample documentation. Transport of the soil samples from the field is then addressed in a discussion of the federal regulations for shipping radioactive materials. Interpretation of those regulations, particularly in light of their application to remedial action soil-sampling programs, is provided in the form of guidance and suggested procedures. Due to the complex nature of the regulations, however, there is no guarantee that our interpretations of them are complete or entirely accurate. Preparation of soil samples for radium-226 analysis by means of gamma-ray spectroscopy is described.

  10. Waste Treatment Plant Overview

    Office of Environmental Management (EM)

    contracted Bechtel National, Inc., to design and build the world's largest radioactive waste treatment plant. The Waste Treatment and Immobilization Plant (WTP), also known as the...

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

    SciTech Connect (OSTI)

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

    2010-10-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    S. Blaine Grover; David A. Petti

    2008-10-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    S. Blaine Grover

    2006-10-01T23:59:59.000Z

    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.

  14. Operating-procedure system at Savannah River Plant

    SciTech Connect (OSTI)

    Tope, C.W.

    1981-05-01T23:59:59.000Z

    Three types of procedures are widely used at SRP: Du Pont Savannah Operating Logsheet, Du Pont Savannah Operating Procedure, and Plant Manual. This document briefly reviews originating of the procedures, their preparation, control, and indexing. (DLC)

  15. Post-Treatment Hemodynamics of a Basilar Aneurysm and Bifurcation

    SciTech Connect (OSTI)

    Ortega, J; Hartman, J; Rodriguez, J; Maitland, D

    2008-01-16T23:59:59.000Z

    Aneurysm re-growth and rupture can sometimes unexpectedly occur following treatment procedures that were initially considered to be successful at the time of treatment and post-operative angiography. In some cases, this can be attributed to surgical clip slippage or endovascular coil compaction. However, there are other cases in which the treatment devices function properly. In these instances, the subsequent complications are due to other factors, perhaps one of which is the post-treatment hemodynamic stress. To investigate whether or not a treatment procedure can subject the parent artery to harmful hemodynamic stresses, computational fluid dynamics simulations are performed on a patient-specific basilar aneurysm and bifurcation before and after a virtual endovascular treatment. The simulations demonstrate that the treatment procedure produces a substantial increase in the wall shear stress. Analysis of the post-treatment flow field indicates that the increase in wall shear stress is due to the impingement of the basilar artery flow upon the aneurysm filling material and to the close proximity of a vortex tube to the artery wall. Calculation of the time-averaged wall shear stress shows that there is a region of the artery exposed to a level of wall shear stress that can cause severe damage to endothelial cells. The results of this study demonstrate that it is possible for a treatment procedure, which successfully excludes the aneurysm from the vascular system and leaves no aneurysm neck remnant, to elevate the hemodynamic stresses to levels that are injurious to the immediately adjacent vessel wall.

  16. Model Recovery Procedure for Response to a Radiological Transportation...

    Office of Environmental Management (EM)

    Incident.docx More Documents & Publications Hazardous Materials Incident Response Procedure First Responder Initial Response Procedure TEPP Model Needs Assessment Document...

  17. POLICY GUIDANCE MEMORANDUM #35 Procedures for Compliance with...

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

    POLICY GUIDANCE MEMORANDUM 35 Procedures for Compliance with Nepotism and Misuse of Position POLICY GUIDANCE MEMORANDUM 35 Procedures for Compliance with Nepotism and Misuse of...

  18. Policy Guidance Memorandum #37 Procedures for Excepted Service...

    Energy Savers [EERE]

    7 Procedures for Excepted Service Exceptionally Well Qualified (EWQ) Appointments Policy Guidance Memorandum 37 Procedures for Excepted Service Exceptionally Well Qualified (EWQ)...

  19. Records Management Procedures for Storage, Transfer and Retrieval...

    Energy Savers [EERE]

    Procedures for Storage, Transfer and Retrieval of Records from WNRC Records Management Procedures for Storage, Transfer and Retrieval of Records from WNRC Develop and maintain a...

  20. ISSUANCE 2015-05-26: Energy Conservation Program: Test Procedures...

    Office of Environmental Management (EM)

    Energy Conservation Program: Test Procedures for Ceiling Fans, Supplemental Notice of Proposed Rule ISSUANCE 2015-05-26: Energy Conservation Program: Test Procedures for Ceiling...

  1. ISSUANCE 2015-06-26: Energy Conservation Program: Test Procedures...

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

    26: Energy Conservation Program: Test Procedures for Dehumidifiers, Final Rule ISSUANCE 2015-06-26: Energy Conservation Program: Test Procedures for Dehumidifiers, Final Rule This...

  2. ENERGY STAR Test Procedures and Verification | Department of...

    Energy Savers [EERE]

    ENERGY STAR ENERGY STAR Test Procedures and Verification ENERGY STAR Test Procedures and Verification The Department of Energy (DOE) is the lead agency in the development and...

  3. Test Procedure for UV Weathering Resistance of Backsheet | Department...

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

    Test Procedure for UV Weathering Resistance of Backsheet Test Procedure for UV Weathering Resistance of Backsheet Presented at the PV Module Reliability Workshop, February 26 - 27...

  4. Energy Conservation Program: Test Procedure for Pumps, Notice...

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

    Conservation Program: Test Procedure for Pumps, Notice of Proposed Rulemaking Energy Conservation Program: Test Procedure for Pumps, Notice of Proposed Rulemaking This document is...

  5. 2014-04-11 Issuance: Test Procedures for Residential Clothes...

    Energy Savers [EERE]

    4-11 Issuance: Test Procedures for Residential Clothes Washers; Notice of Proposed Rulemaking 2014-04-11 Issuance: Test Procedures for Residential Clothes Washers; Notice of...

  6. 2014-10-16 Issuance: Energy Conservation Program Test Procedures...

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

    16 Issuance: Energy Conservation Program Test Procedures for Residential Clothes Dryers, Notice of Public Meeting 2014-10-16 Issuance: Energy Conservation Program Test Procedures...

  7. Meeting Concerning Potential Test Procedures and Energy Conservation...

    Energy Savers [EERE]

    Meeting Concerning Potential Test Procedures and Energy Conservation Standards for Set-Top Boxes and Network Equipment Meeting Concerning Potential Test Procedures and Energy...

  8. 2014-10-29 Issuance: Energy Conservation Program: Test Procedures...

    Office of Environmental Management (EM)

    9 Issuance: Energy Conservation Program: Test Procedures for External Power Supplies, Notice of Public Meeting 2014-10-29 Issuance: Energy Conservation Program: Test Procedures for...

  9. 2014-04-10 Issuance: Test Procedures for Commercial Refrigeration...

    Energy Savers [EERE]

    04-10 Issuance: Test Procedures for Commercial Refrigeration Equipment; Final Rule 2014-04-10 Issuance: Test Procedures for Commercial Refrigeration Equipment; Final Rule This...

  10. 2014-11-26 Issuance: Test Procedures for Miscellaneous Refrigeration...

    Office of Environmental Management (EM)

    6 Issuance: Test Procedures for Miscellaneous Refrigeration Products; Notice of Proposed Rulemaking 2014-11-26 Issuance: Test Procedures for Miscellaneous Refrigeration Products;...

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

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

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

  12. Argonne Facilitation of PHEV Standard Testing Procedure (SAE...

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

    Argonne Facilitation of PHEV Standard Testing Procedure (SAE J1711) Argonne Facilitation of PHEV Standard Testing Procedure (SAE J1711) 2009 DOE Hydrogen Program and Vehicle...

  13. Leave Entitlements for Managerial and Bargaining Unit (AFT) Professional Employees Procedure ADMINISTRATIVE PROCEDURE

    E-Print Network [OSTI]

    Rainforth, Emma C.

    Leave Entitlements for Managerial and Bargaining Unit (AFT) Professional Employees Procedure 1 ADMINISTRATIVE PROCEDURE 3/28/13 Leave Entitlements for Managerial and Bargaining Unit (AFT) Professional in advance. Vacation allowance must be taken during the current year, (calendar year for bargaining unit

  14. Chapter 10. Dissertation defence procedure Section 1. Dissertation defence procedure at the University of

    E-Print Network [OSTI]

    van der Torre, Leon

    Chapter 10. Dissertation defence procedure Section 1. Dissertation defence procedure at the University of Luxembourg Article IV.10.101. Before the defence. The dissertation shall be written in one by the topic, the dissertation may be written in Luxembourgish or, with the authorisation of the rector

  15. Summative Mass Analysis of Algal Biomass - Integration of Analytical Procedures: Laboratory Analytical Procedure (LAP)

    SciTech Connect (OSTI)

    Laurens, L. M. L.

    2013-12-01T23:59:59.000Z

    This procedure guides the integration of laboratory analytical procedures to measure algal biomass constituents in an unambiguous manner and ultimately achieve mass balance closure for algal biomass samples. Many of these methods build on years of research in algal biomass analysis.

  16. Coordinate Measuring Machine Pit Artifact Inspection Procedure

    SciTech Connect (OSTI)

    Montano, Joshua D. [Los Alamos National Laboratory

    2012-07-31T23:59:59.000Z

    The goal of this document is to outline a procedure for dimensional measurement of Los Alamos National Laboratory's CMM Pit Artifact. This procedure will be used by the Manufacturing Practice's Inspection Technology Subgroup of the Interagency Manufacturing Operations Group and Joint Operations Weapon Operations Group (IMOG/JOWOG 39) round robin participants. The intent is to assess the state of industry within the Nuclear Weapons Complex for measurements made on this type of part and find which current measurement strategies and techniques produce the best results.

  17. CUNY EXPORT CONTROL PROCEDURES 7. Human Resources

    E-Print Network [OSTI]

    Rosen, Jay

    CUNY EXPORT CONTROL PROCEDURES 7. Human Resources This section addresses the I-129 certification process for visa applicants4 who may have access to export controlled items. It also addresses the process) will require an export license to access export controlled technology or technical data during the course

  18. CUNY EXPORT CONTROL PROCEDURES 18. Record Keeping

    E-Print Network [OSTI]

    Rosen, Jay

    CUNY EXPORT CONTROL PROCEDURES 18. Record Keeping Export control records must be retained export control-related recordkeeping. These records must be organized so as to be available when of export or from the date of license expiration, as per the requirements of ITAR Section 123.22 and EAR

  19. CUNY EXPORT CONTROL PROCEDURES 16. Travel Abroad

    E-Print Network [OSTI]

    Rosen, Jay

    CUNY EXPORT CONTROL PROCEDURES 16. Travel Abroad This Section addresses the process for ensuring export control compliance when shipping or carrying tangible items associated with conferences with whether these activities are subject to export control regulations, to the extent that the scope

  20. CUNY EXPORT CONTROL PROCEDURES 13. Sponsored Research

    E-Print Network [OSTI]

    Rosen, Jay

    CUNY EXPORT CONTROL PROCEDURES 13. Sponsored Research This Section addresses the export control or contract contains or triggers export control restrictions. In general, CUNY does not accept restrictions with regard to export controls or the control implication of a particular clause or set of clauses may

  1. Combining Decision Procedures for Sorted Theories

    E-Print Network [OSTI]

    Tinelli, Cesare

    setting, nor is it obvious that the method in fact lifts as is to logics with sorts. To bridge this gap decision procedures for logical theories arises in many areas of computer science and artificial to Nelson and Oppen [8]. This method is at the heart of the verification systems cvc [9], argo-lib [6

  2. Risk Management Procedures Category: Strategic Management

    E-Print Network [OSTI]

    1 Risk Management Procedures Category: Strategic Management 1. LEGISLATION/ENTERPRISE AGREEMENT/POLICY SUPPORTED Risk Management Policy Tertiary Education Quality Standards Agency Act 2011 (TEQSA Act 2011) 2 (a) Advise the Vice-Chancellor on the effective management of the University's risk profile

  3. PHYSICAL PLANT OPERATING POLICY AND PROCEDURE

    E-Print Network [OSTI]

    Gelfond, Michael

    in this technology. REVIEW This Physical Plant Operating Policy/Procedure (PP/OP) will be reviewed in March of each Plant. Physical Plant's intention is to provide each employee reasonable access to the technology Plant technology will be a prime consideration. Requests for non-standard products will not be approved

  4. Fabrication Procedures and Process Sensitivities for

    E-Print Network [OSTI]

    with an AM1.5 eciency of 15.4% as verified by the National Renewable Energy Laboratory. SOLAR CELL Avenue, Toledo, OH 43607, U.S.A. Contract/grant sponsor: U.S. Department of Energy; Contract/grant numberFabrication Procedures and Process Sensitivities for CdS/CdTe Solar Cells Doug H. Rose*, Falah S

  5. Energy Audit Procedures Prepared for the

    E-Print Network [OSTI]

    Energy Audit Procedures Prepared for the U.S. Department of Energy Office of Electricity Delivery Subtask 3.5.1: Residential Energy Efficiency Deliverable 1 Prepared by The University of Hawai or reflect those of the United States Government or any agency thereof. #12;Project Report 1: Energy Audit

  6. Detailed Financial Procedures Page 1 of 3

    E-Print Network [OSTI]

    Levi, Ran

    Detailed Financial Procedures Page 1 of 3 Inventories and Disposals Background In accordance with Standing Financial Regulation, Heads of Departments are responsible for maintaining inventories for all disposals thereof. (Ref 8.03 & 8.06) Inventory Spreadsheet The following information should be recorded

  7. BU BRAIN Self Service GRADING PROCEDURES

    E-Print Network [OSTI]

    Suzuki, Masatsugu

    1 BU BRAIN Self Service GRADING PROCEDURES FOR FACULTY Updated May 2014/PD #12;2 Table of Contents BRAIN Self Service icon on left side of page: #12;4 Entering Grades: Once in BU BRAIN Self Service, go BRAIN Self Service; Registered ­ student registered through the department). Grade: Student's grade

  8. ANNUAL INVENTORY PROCEDURES INVENTORY WORKSHEET RETURN

    E-Print Network [OSTI]

    Provancher, William

    ANNUAL INVENTORY PROCEDURES INVENTORY WORKSHEET RETURN Inventories are to be completed and returned is e-mailed to Inventory Controller If inventory is not returned by due date: · Two weeks after due date, request for return is e-mailed to Inventory Controller · One month after due date, e

  9. Internship FBI Fingerprint Procedures and Additional Screenings

    E-Print Network [OSTI]

    Gering, Jon C.

    Internship FBI Fingerprint Procedures and Additional Screenings ALL INTERNS: Required by DESE/Full-Year Internship) or August 1st (Spring Internship) o Web application https to get your fingerprints taken for your internship: 4 digit Registration #2301 Cost - $44.80 Valid

  10. Animal Care and Biosafety STANDARD OPERATING PROCEDURES

    E-Print Network [OSTI]

    Animal Care and Biosafety Committee 1 STANDARD OPERATING PROCEDURES BUACBC-SOP-01 Fish technique for fish species. 1. Materials 1. Water, MS222TM A. Considerations 1. Tricane methanesulphonate (MS222TM) is one of the few anaesthetic registered for veterinary use on fish in Canada and has

  11. UNIVERSITY OF NORTHERN BRITISH COLUMBIA Policies & Procedures

    E-Print Network [OSTI]

    Bolch, Tobias

    UNIVERSITY OF NORTHERN BRITISH COLUMBIA Policies & Procedures Facilities ­ Parking Services or under the charge or control of the University of Northern British Columbia hereinafter referred.2 Authorization A parking permit conveys the authorization by the University of Northern British Columbia

  12. UNIVERSITY OF NORTHERN BRITISH COLUMBIA Policies & Procedures

    E-Print Network [OSTI]

    Bolch, Tobias

    UNIVERSITY OF NORTHERN BRITISH COLUMBIA Policies & Procedures Services President's Council Page 1, including vending, will be administered by the University of Northern British Columbia. Food and beverage will be contracted out to one or more qualified contractors. All university catering under the current Food

  13. Special Access Program Policies, Responsibilities, and Procedures

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

    2002-07-11T23:59:59.000Z

    Special Access Program Policies, Responsibilities, and Procedures This Manual is for OFFICIAL USE ONLY and will not be distributed on the Directives Portal. For distribution, please contact the Director, Office of Security, at 202-586-6775. Cancels: DOE M 471.2-3

  14. LASER SAFETY MANUAL POLICIES AND PROCEDURES

    E-Print Network [OSTI]

    Zhang, Yuanlin

    LASER SAFETY MANUAL POLICIES AND PROCEDURES FOR LASER SAFETY AT TEXAS TECH UNIVERSITY LUBBOCK, TEXAS September 2002 #12;V-1 TEXAS TECH UNIVERSITY LASER SAFETY MANUAL TABLE OF CONTENTS SECTION I ­ MANAGEMENT OF LASER LICENSE Introduction A. Laser Safety Program I - 1 B. Radiation Laser Safety Committee I

  15. Security Procedures Caltech Campus Security Dispatch

    E-Print Network [OSTI]

    Goddard III, William A.

    Security Procedures Caltech Campus Security Dispatch: 5000 (from any Caltech phone) or (626) 395-5000 (from any phone) When emergencies arise, contact Caltech Campus Security MEDICAL If someone experiences a medical emergency: · Remain calm · Notify Campus Security Dispatch · Do NOT move victim EARTHQUAKE When

  16. FSU Property Scanning Procedures To Scan Barcodes

    E-Print Network [OSTI]

    McQuade, D. Tyler

    1 of 3 FSU Property Scanning Procedures To Scan Barcodes: 1) To power up the scanner BLUE=CONTINUE ESC=DONE 4) Press the yellow button to scan your FSU location tag. When the location tag has been successfully scanned you will hear a beep and the display will look like this: ITEM

  17. Student Disability Transportation Policies and Procedures

    E-Print Network [OSTI]

    Portman, Douglas

    Student Disability Transportation Policies and Procedures Enrolled students with a permanent or temporary disability that require transportation while on-campus, should submit an application form through the University Health Service office. If approved through UHS, the transportation coordinator will contact you

  18. PROCEDURES FOR ALLOCATION AND AGGREGATION OF RESOURCES

    E-Print Network [OSTI]

    Laughlin, Robert B.

    Chapter AA PROCEDURES FOR ALLOCATION AND AGGREGATION OF RESOURCES By Ronald R. Charpentier, T.......................................................................................................AA-7 Appendix 1 Aggregation of Undiscovered Oil, Gas, and NGL Volumes Of Regions to World Total Monte RH. The separate reporting of onshore versus offshore undiscovered resources is important to economic

  19. The Psychology Clinic Manual of Procedures and

    E-Print Network [OSTI]

    Zhang, Yuanlin

    and Maintenance of Test Security 10.6 Obtaining Assessment Materials 10.7 Standard Assessment Protocol 10.8 CourseTEXAS TECH UNIVERSITY The Psychology Clinic Manual of Procedures and Requirements FALL 2013 Edition Statement 1.3 Faculty and Staff 1.4 Contact Information 1.5 Hours of Operation 1.6 Parking 1.7 Clinic

  20. Chemical Hygiene Policy Procedure: 6.05

    E-Print Network [OSTI]

    Jia, Songtao

    Chemical Hygiene Policy Procedure: 6.05 Version: 1.0 Created: 6/15/2013 1 A. Purpose: The Chemical Hygiene policy establishes Columbia University's position for the protection of laboratory workers and emergency response. For details and further requirements consult the Columbia University Chemical Hygiene

  1. POLICY AND PROCEDURE MANUAL DENTAL HYGIENE STUDENT

    E-Print Network [OSTI]

    Nickrent, Daniel L.

    Page | 1 POLICY AND PROCEDURE MANUAL FOR THE DENTAL HYGIENE STUDENT DENTAL HYGIENE PROGRAM SCHOOL for the Dental Hygiene Student." The contents have been explained to me, and I have been given the opportunity to abide by the requirements of this document as long as I remain a Dental Hygiene Student at Southern

  2. Fusion procedure for the Brauer algebra

    E-Print Network [OSTI]

    A. P. Isaev; A. I. Molev

    2008-12-22T23:59:59.000Z

    We show that all primitive idempotents for the Brauer algebra B_n(w) can be found by evaluating a rational function in several variables which has the form of a product of R-matrix type factors. This provides an analogue of the fusion procedure for B_n(w).

  3. Safe Operating Procedure (Revised 10/11)

    E-Print Network [OSTI]

    Farritor, Shane

    and Countermeasures (SPCC) Plans or to storm water best management practices (BMPs). It is intended to provide those) & STORM WATER BMPS SPILL/RELEASE PREPARATION & RESPONSE. Response Procedures Under UNL's SPCC Plans and storm water BMPs, two scenarios are planned for oil spills

  4. Dartmouth College Employment Policies and Procedures Manual

    E-Print Network [OSTI]

    Myers, Lawrence C.

    Dartmouth College Employment Policies and Procedures Manual Policy last updated: Dec 1, 2006 Employment of Minors Applies to: All current and prospective employees under the age of 18 Policy Statement: The College follows state and federal laws governing the employment of minors. Per New Hampshire law, children

  5. Safe Operating Procedure (Reviewed 7/09)

    E-Print Network [OSTI]

    Farritor, Shane

    for disposal of hazardous and/or radioactive wastes are to be followed. Ca- 45 waste should be segregated fromSafe Operating Procedure (Reviewed 7/09) SAFETY PROTOCOL: Ca-45://ehs.unl.edu/) Use of radioactive materials requires a safety protocol be submitted to the UNL Radiation Safety

  6. Safe Operating Procedure (Reviewed 7/09)

    E-Print Network [OSTI]

    Farritor, Shane

    for disposal of hazardous and/or radioactive wastes are to be followed. Cl-36 waste should be segregated fromSafe Operating Procedure (Reviewed 7/09) SAFETY PROTOCOL: Cl-36://ehs.unl.edu/) Use of radioactive materials requires a safety protocol be submitted to the UNL Radiation Safety

  7. Safe Operating Procedure (Reviewed 7/09)

    E-Print Network [OSTI]

    Farritor, Shane

    of hazardous and/or radioactive wastes are to be followed. C-14 waste can be combined with H-3 wasteSafe Operating Procedure (Reviewed 7/09) SAFETY PROTOCOL: C-14://ehs.unl.edu/) Use of radioactive materials requires a safety protocol be submitted to the UNL Radiation Safety

  8. Human Resources FLEXIBLE RETIREMENT POLICY AND PROCEDURE

    E-Print Network [OSTI]

    Doran, Simon J.

    %. Pension benefits taken before the schemes' normal pension age may be subject to an early retirement1 of 10 Human Resources May 2012 FLEXIBLE RETIREMENT POLICY AND PROCEDURE #12;2 of 10 1. Purpose of the University Pension schemes which operates a flexible retirement scheme, and establishes guidelines

  9. 1983 EML Procedures Manual. 26th Edition

    SciTech Connect (OSTI)

    Volchok, H.L.; de Planque, G. (eds.)

    1983-01-01T23:59:59.000Z

    This document consists of page and section changes to the following HASL-300 procedures: fallout collection methods, radiochemical /sup 90/Sr, atomic absorption-emission spectrophotometry of trace metals, precipitation and lake water samples, anions by ion chromatography, polynuclear aromatic hydrocarbons in sediments, Mn in saline precipitation samples, and Pb in saline precipitation samples. (DLC)

  10. Student Regulations and Procedures Academic Division

    E-Print Network [OSTI]

    Student Regulations and Procedures Academic Division 2007/2008 11 Students Union Code information regarding their course, tuition fees, award ceremonies and other matters www.mmu.ac.uk/academic's Articles of Government (Article 1.1). As prescribed in the Articles of Government (Article 12

  11. Student Regulations and Procedures Academic Division

    E-Print Network [OSTI]

    Student Regulations and Procedures Academic Division 2007/2008 3 RULES FOR STUDENT CONDUCT fees, award ceremonies and other matters www.mmu.ac.uk/academic/student_regulations.php #12;RULES of Governors in accordance with the following Articles of Government: 7.1.6 Subject to the responsibilities

  12. Chemical Spill Response Procedure Initial Response

    E-Print Network [OSTI]

    Chemical Spill Response Procedure Initial Response 1. Advise lab occupants of the spill-4500. If not, continue with step 4. Clean-Up 4. Ensure the spill area has adequate ventilation to clear gases is absorbed. If necessary, add more neutralizing powder. 9. If cleaning up a solvent, proceed to step 13. 10

  13. Page 1 of 5 OUA CSP Procedures

    E-Print Network [OSTI]

    Page 1 of 5 OUA CSP Procedures Author(s): Kayla Polak Date Issued: March 2013 Issuing Area: Flexible Learning Support Subject: OUA Commonwealth Supported Places (CSP) Circulation: University OUA CSP award courses. As the Flexible Learning Support office at Curtin University is the conduit

  14. Page 1 of 3 OUA results procedures

    E-Print Network [OSTI]

    Offices Review Date: June 2014 Background As a result of the creation of Badged and CSP courses, there has, they are: · Generic, · Badged, · CSP (standard) and · CSP (Not For Degree [NFD]) In addition according to internal procedure, then hold a BOE and ratify results. CSP Standard FLS create a .csv version

  15. 3741SPACE AUDIT PROCEDURE Space audit

    E-Print Network [OSTI]

    Page 1 3741SPACE AUDIT PROCEDURE Space audit identified to be conducted Will audit disrupt or disturb occupants of the space Notify Faculty, School or Business Unit of the audit Is the audit for timetabling purposes Is the audit a physical audit Confirm audit requirements Is the audit for other space

  16. 3740SPACE REPURPOSING PROCEDURE Client identifies

    E-Print Network [OSTI]

    Page 1 3740SPACE REPURPOSING PROCEDURE Client identifies space repurposing requirement Client completes space request form Submit space request form to Space Management Office Space Management Office acknowledge reciept Is space form completed accurately Space Management Office conduct space analysis Does

  17. Awards and Fellowships Nomination Submission Procedures

    E-Print Network [OSTI]

    Indiana University

    Awards and Fellowships Nomination Submission Procedures University Graduate School #12;SharePoint Site The University Graduate School has created a SharePoint site for the submission of award to your favorites #12;How to Submit a Nomination 2. Click the Award and Fellowship Nominations link under

  18. PHYSICAL PLANT OPERATING POLICY AND PROCEDURE

    E-Print Network [OSTI]

    Gelfond, Michael

    natural gas supply contract and gas transportation agreement when required for Texas Tech UniversityPHYSICAL PLANT OPERATING POLICY AND PROCEDURE PP/OP 05.09: Gas Supply and Transportation Contract, 2010 Page 2 PP/OP 05.09 d. Gas Transportation Agreement - Two main gas transportation lines serve

  19. COMMONWEALTH OF VIRGINIA EMPLOYEE GRIEVANCE PROCEDURE

    E-Print Network [OSTI]

    Swaddle, John

    Dispute Resolution (EDR) may be contacted if questions arise. Check if you decided not to present want the agency head to determine whether I have access to the grievance procedure. I want EDR to rule-371-7318 www.edr.state.va.us #12;III. Second Resolution Step Date Received: Date of Meeting: Response: Date

  20. COMMONWEALTH OF VIRGINIA EMPLOYEE GRIEVANCE PROCEDURE

    E-Print Network [OSTI]

    Swaddle, John

    Procedure Manual for specific instructions. The Department of Employment Dispute Resolution (EDR) may-371-7318 www.edr.state.va.us #12;II. Second Resolution Step Date Received: Date of Meeting: Response: Date want EDR to rule on whether I initiated my grievance in 30 calendar days. Employee's comments (optional

  1. FRENCH APPROVAL PROCEDURES FOR PYROTECHNICAL AUTOMOTIVE SAFETY

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    FRENCH APPROVAL PROCEDURES FOR PYROTECHNICAL AUTOMOTIVE SAFETY EQUIPMENTS Lionel Aufauvre*, Ruddy and that are not excluded of the decree application have to conform to approved types. Pyrotechnical automotive safety appeared in automotive industry and their uses grew rapidly as they showed their efficiency to save lives

  2. Animal Care and Biosafety STANDARD OPERATING PROCEDURES

    E-Print Network [OSTI]

    for use within the given animal tank; 3. NO PLASTIC TANKS WILL HAVE HEATERS! 4. ALL tanks containing glasses and nitrile gloves. #12;BUACBCSOP05 2 4. Procedure A. Aquarium Maintenance: 1. Water changes. I. 2025% of the tank water will be replaced weekly and 50% monthly. The water must

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

    SciTech Connect (OSTI)

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

    2012-07-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

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

    2012-07-01T23:59:59.000Z

    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)

  5. Acceptance test procedure for the overview video camera system (OVS)

    SciTech Connect (OSTI)

    Pardini, A.F.

    1995-10-01T23:59:59.000Z

    Acceptance Test Procedure for testing the Light Duty Utility Arm (LDUA) Overview Video Camera System (OVS).

  6. STANDARD OPERATING PROCEDURES Sampler Maintenance by Site Operators

    E-Print Network [OSTI]

    Fischer, Emily V.

    IMPROVE STANDARD OPERATING PROCEDURES SOP 201 Sampler Maintenance by Site Operators Date Last.0 PURPOSE AND APPLICABILITY This standard operating procedure (SOP) describes the procedures and schedules. The procedural steps for weekly maintenance and repairs performed by the site operator are included in TI 201A

  7. Policy and Procedure Writing Tips University Policy Website

    E-Print Network [OSTI]

    Pedersen, Tom

    Policy and Procedure Writing Tips University Policy Website Policy and Procedure Writing Tips Updated May 2009 Page 1 of 2 · Differentiate between policies and procedures. o University Policies review and approval for policy issuance and revision. o University Procedures are the processes

  8. The Waste Management Quality Assurance Implementing Management Plan (QAIMP)

    E-Print Network [OSTI]

    Albert editor, R.

    2009-01-01T23:59:59.000Z

    Qualification and certification requirements for procedures, specifications, and personnel EquipmentQualification and certification requirements of test personnel. Type of testing and measuring equipment

  9. 34.07.99.M0.02 Bomb Threat Procedures Page 1 of 3 STANDARD ADMINISTRATIVE PROCEDURE

    E-Print Network [OSTI]

    34.07.99.M0.02 Bomb Threat Procedures Page 1 of 3 STANDARD ADMINISTRATIVE PROCEDURE 34.07.99.M0.02 Bomb Threat Procedures Approved September 25, 2001 Revised April 30, 2010 Next scheduled review: April 4, 2016 Standard Administrative Procedure Statement Any and all bomb threats are regarded seriously

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

    E-Print Network [OSTI]

    Hickman, Mark

    ; quantitative and qualitative risk analysis; ethical issues and risk communication; applications and case: Risk concepts; context and perceptions; risk identification, analysis, evaluation and treatment. Wildland fires, fire investigation, fire-fighting. ENFE601: Fire resistance and the behaviour, analysis

  11. Procedure to Measure Indoor Lighting Energy Performance

    SciTech Connect (OSTI)

    Deru, M.; Blair, N.; Torcellini, P.

    2005-10-01T23:59:59.000Z

    This document provides standard definitions of performance metrics and methods to determine them for the energy performance of building interior lighting systems. It can be used for existing buildings and for proposed buildings. The primary users for whom these documents are intended are building energy analysts and technicians who design, install, and operate data acquisition systems, and who analyze and report building energy performance data. Typical results from the use of this procedure are the monthly and annual energy used for lighting, energy savings from occupancy or daylighting controls, and the percent of the total building energy use that is used by the lighting system. The document is not specifically intended for retrofit applications. However, it does complement Measurement and Verification protocols that do not provide detailed performance metrics or measurement procedures.

  12. Nondestructive assay (NDA) techniques and procedures

    SciTech Connect (OSTI)

    Not Available

    1994-05-01T23:59:59.000Z

    Report No. 4 is precursory to Report No. 5 {open_quotes}Determination of the Quantity and Locations of the Pu Currently Retained in the Cimarron Fuel Plant Systems{close_quotes} which will be presented upon completion of the decontamination of the Cimarron Plutonium Fuel Fabrication Facility. This report presents the Non-Destructive Assay (NDA) procedures which were developed and used by Sequoyah Fuels Corporation (successor to Kerr-McGee Nuclear Corporation) to measure equipment hold-up of plutonium materials for inventory purposes during operation of the plant. These procedures are also used to measure plutonium contamination on the equipment removed from the Material Balance Areas (MBA`s) during final decontamination. Report No. 5 will compare the measurements taken during this final decontamination period to previous inventory hold-up measurements, the date will be statistically analyzed, and a long-term assessment of the performance of the NDA equipment will be described.

  13. Onsite Wastewater Treatment Systems: Aerobic Treatment Unit

    E-Print Network [OSTI]

    Lesikar, Bruce J.

    2008-10-31T23:59:59.000Z

    Aerobic units treat wastewater using the same process, only scaled down, as municipal wastewater treatment systems. This publication explains how aerobic units work, what their design requirements are, and how to maintain them....

  14. Characterization of aerosols produced by surgical procedures

    SciTech Connect (OSTI)

    Yeh, H.C.; Muggenburg, B.A.; Lundgren, D.L.; Guilmette, R.A.; Snipes, M.B.; Jones, R.K. [Inhalation Toxicology Research Institute, Albuquerque, NM (United States); Turner, R.S. [Lovelace Health Systems, Albuquerque, NM (United States)

    1994-07-01T23:59:59.000Z

    In many surgeries, especially orthopedic procedures, power tools such as saws and drills are used. These tools may produce aerosolized blood and other biological material from bone and soft tissues. Surgical lasers and electrocautery tools can also produce aerosols when tissues are vaporized and condensed. Studies have been reported in the literature concerning production of aerosols during surgery, and some of these aerosols may contain infectious material. Garden et al. (1988) reported the presence of papilloma virus DNA in the fumes produced from laser surgery, but the infectivity of the aerosol was not assessed. Moon and Nininger (1989) measured the size distribution and production rate of emissions from laser surgery and found that particles were generally less than 0.5 {mu}m diameter. More recently there has been concern expressed over the production of aerosolized blood during surgical procedures that require power tools. In an in vitro study, the production of an aerosol containing the human immunodeficiency virus (HIV) was reported when power tools were used to cut tissues with blood infected with HIV. Another study measured the size distribution of blood aerosols produced by surgical power tools and found blood-containing particles in a number of size ranges. Health care workers are anxious and concerned about whether surgically produced aerosols are inspirable and can contain viable pathogens such as HIV. Other pathogens such as hepatitis B virus (HBV) are also of concern. The Occupational Safety and Health funded a project at the National Institute for Inhalation Toxicology Research Institute to assess the extent of aerosolization of blood and other tissues during surgical procedures. This document reports details of the experimental and sampling approach, methods, analyses, and results on potential production of blood-associated aerosols from surgical procedures in the laboratory and in the hospital surgical suite.

  15. Roof Coating Procedures and Their Productivity Gains

    E-Print Network [OSTI]

    Bonaby, J.; Schaub, D.

    2006-01-01T23:59:59.000Z

    benefit of the installation of different roof coating technologies and comparable application procedures of these technologies are ambiguous. The focal point of this research is to determine the effective correlation between various commercially... available roof coatings, and productivity gains associated with these energy saving strategies. This type of situation is evidenced in the justification of energy rebates distributed by Florida Power & Light in exchange for the application of Energy Star...

  16. TOUGH2 Software Qualification

    E-Print Network [OSTI]

    2010-01-01T23:59:59.000Z

    EOS5 (Water, Hydrogen): This property module was developed8. ThermophysicaZ Properties of Hydrogen Density at P=l barby hydrogen, with different thermophysical properties (see

  17. TOUGH2 Software Qualification

    E-Print Network [OSTI]

    2010-01-01T23:59:59.000Z

    mass transport in the Cerro Prieto geothermal field, Mexico,Quantitative Model of the Cerro Prieto Field," Proceedingsexploited reservoirs of the Cerro Prieto geothermal systems,

  18. TOUGH2 Software Qualification

    E-Print Network [OSTI]

    2010-01-01T23:59:59.000Z

    and Heat Flow in Fractured Reservoirs, Soc. Pet. EngineersBehavior of Naturally Fractured Reservoirs, Soc. Pet. Eng.Flow Simulations in Fractured Reservoirs, Report LBL-15227,

  19. ITOUGH2 Software Qualification

    E-Print Network [OSTI]

    Fraser, P.

    2010-01-01T23:59:59.000Z

    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

  20. TOUGH2 Software Qualification

    E-Print Network [OSTI]

    2010-01-01T23:59:59.000Z

    induced by nuclear heat-generating waste packages in afluid and heat flow processes in nuclear waste isolation, W.Fluid and Heat Flow Near High-Level Nuclear Waste Packages

  1. ITOUGH2 Software Qualification

    E-Print Network [OSTI]

    Fraser, P.

    2010-01-01T23:59:59.000Z

    wet, almost flowing mudflat sediments and root- dominatedthe largest expanse of mudflat possible. In the laboratory,sediments on the surface of mudflat region are resuspended,

  2. Chemical Processing Qualification Standard

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011AT&T, Inc.'sEnergyTexas1. Feedstock & ProductionChapter 6 LosChelsea20106-2010

  3. 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 onYouTube YouTube Note: Since the.pdfBreakingMay 2015 < prev nextEnergyCanadian Hydropower

  4. 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 DataDepartment of Energy Your Density Isn't YourTransport(FactDepartment3311, 3312), October 20122Technologies61-2008 June 2008 DOE STANDARD

  5. 978-1-4244-2953-0/09/$25.00 2009 IEEE 360 10th Int'l Symposium on Quality Electronic Design Accelerating Jitter Tolerance Qualification for High Speed Serial Interfaces

    E-Print Network [OSTI]

    Zilic, Zeljko

    Accelerating Jitter Tolerance Qualification for High Speed Serial Interfaces Yongquan Fan and Zeljko Zilic of HSSIs are critical to guarantee the design quality and the device quality. Jitter tolerance at 10-12 Bit considers an acceleration scheme to quantify post-silicon jitter tolerance. It can reduce the test time from

  6. The attractor mechanism as a distillation procedure

    E-Print Network [OSTI]

    Péter Lévay; Szilárd Szalay

    2010-04-14T23:59:59.000Z

    In a recent paper it has been shown that for double extremal static spherically symmetric BPS black hole solutions in the STU model the well-known process of moduli stabilization at the horizon can be recast in a form of a distillation procedure of a three-qubit entangled state of GHZ-type. By studying the full flow in moduli space in this paper we investigate this distillation procedure in more detail. We introduce a three-qubit state with amplitudes depending on the conserved charges the warp factor, and the moduli. We show that for the recently discovered non-BPS solutions it is possible to see how the distillation procedure unfolds itself as we approach the horizon. For the non-BPS seed solutions at the asymptotically Minkowski region we are starting with a three-qubit state having seven nonequal nonvanishing amplitudes and finally at the horizon we get a GHZ state with merely four nonvanishing ones with equal magnitudes. The magnitude of the surviving nonvanishing amplitudes is proportional to the macroscopic black hole entropy. A systematic study of such attractor states shows that their properties reflect the structure of the fake superpotential. We also demonstrate that when starting with the very special values for the moduli corresponding to flat directions the uniform structure at the horizon deteriorates due to errors generalizing the usual bit flips acting on the qubits of the attractor states.

  7. Some Sequential Procedures for Selecting the Better Bernoulli Treatment by Using a Matched Samples Design

    E-Print Network [OSTI]

    Bustamante, Fabián E.

    Design Author(s): Ajit C. Tamhane Source: Journal of the American Statistical Association, Vol. 80, No. 390 (Jun., 1985), pp. 455- 460 Published by: American Statistical Association Stable URL: http of scholarship. For more information about JSTOR, please contact support@jstor.org. American Statistical

  8. Electric generating or transmission facility: determination of rate-making principles and treatment: procedure (Kansas)

    Broader source: Energy.gov [DOE]

    This legislation permits the KCC to determine rate-making principles that will apply to a utility’s investment in generation or transmission before constructing a facility or entering into a...

  9. Measurement and Treatment of Nuisance Odors at Wastewater Treatment Plants

    E-Print Network [OSTI]

    Abraham, Samantha Margaret

    2014-01-01T23:59:59.000Z

    the ability of existing treatment technologies at Plant 1 toof existing treatment technologies at both OCSD plantsof existing treatment technologies at both OCSD plants

  10. Retrospective review of Contura HDR breast cases to improve our standardized procedure

    SciTech Connect (OSTI)

    Iftimia, Ileana, E-mail: Ileana.n.iftimia@lahey.org [Lahey Clinic, Radiation Oncology Department, MA (United States); Cirino, Eileen T.; Ladd, Ron; Mower, Herbert W.; McKee, Andrea B. [Lahey Clinic, Radiation Oncology Department, MA (United States)

    2013-07-01T23:59:59.000Z

    To retrospectively review our first 20 Contura high dose rate breast cases to improve and refine our standardized procedure and checklists. We prepared in advance checklists for all steps, developed an in-house Excel spreadsheet for second checking the plan, and generated a procedure for efficient contouring and a set of optimization constraints to meet the dose volume histogram criteria. Templates were created in our treatment planning system for structures, isodose levels, optimization constraints, and plan report. This study reviews our first 20 high dose rate Contura breast treatment plans. We followed our standardized procedure for contouring, planning, and second checking. The established dose volume histogram criteria were successfully met for all plans. For the cases studied here, the balloon-skin and balloon-ribs distances ranged between 5 and 43 mm and 1 and 33 mm, respectively; air{sub s}eroma volume/PTV{sub E}val volume?5.5% (allowed?10%); asymmetry<1.2 mm (goal?2 mm); PTV{sub E}val V90%?97.6%; PTV{sub E}val V95%?94.9%; skin max dose?98%Rx; ribs max dose?137%Rx; V150%?29.8 cc; V200%?7.8 cc; the total dwell time range was 225.4 to 401.9 seconds; and the second check agreement was within 3%. Based on this analysis, more appropriate ranges for the total dwell time and balloon diameter tolerance were found. Three major problems were encountered: balloon migration toward the skin for small balloon-to-skin distances, lumen obstruction, and length change for the flexible balloon. Solutions were found for these issues and our standardized procedure and checklists were updated accordingly. Based on our review of these cases, the use of checklists resulted in consistent results, indicating good coverage for the target without sacrificing the critical structures. This review helped us to refine our standardized procedure and update our checklists.

  11. Operation and Maintenance Manual for the Central Facilities Area Sewage Treatment Plant

    SciTech Connect (OSTI)

    Norm Stanley

    2011-02-01T23:59:59.000Z

    This Operation and Maintenance Manual lists operator and management responsibilities, permit standards, general operating procedures, maintenance requirements and monitoring methods for the Sewage Treatment Plant at the Central Facilities Area at the Idaho National Laboratory. The manual is required by the Municipal Wastewater Reuse Permit (LA-000141-03) the sewage treatment plant.

  12. A procedure for oscillatory parameter identification

    SciTech Connect (OSTI)

    Trudnowski, D.J.; Donnelly, M.K. [Pacific Northwest Lab., Richland, WA (United States); Hauer, J.F. [Bonneville Power Administration, Portland, OR (United States)

    1994-02-01T23:59:59.000Z

    A procedure is proposed where a power system is excited with a low-level pseduo-random probing signal and the frequency, damping, magnitude, and shape of oscillatory modes are identified using spectral density estimation and frequency-domain transfer-function identification. Attention is focussed on identifying system modes in the presence of noise. Two examples cases are studied: identification of electromechanical oscillation modes in a 16-machine power system; and turbine-generator shaft modes of a 3-machine power plant feeding a series-compensated 500-kV network.

  13. Procedures for Departing Employees | 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2 OPAM615_CostNSAR - T enAmountCammieReserveSecretaryProcedures for Departing

  14. Records Management Exit Procedures | 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2 OPAM615_CostNSAR - TProcuringDepartmentDepartmentEnergyExit Procedures

  15. Procedures for Departing Employees | Department of Energy

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33Frequently20,000 RussianBy: ThomasDepartment ofThis weekSpecificThat SaveForRM Exit Procedures

  16. CUNY EXPORT CONTROL PROCEDURES 9. Information Technology (IT)

    E-Print Network [OSTI]

    Rosen, Jay

    CUNY EXPORT CONTROL PROCEDURES 9. Information Technology (IT) This Section addresses the process for protecting export controlled proprietary technical data and when these protections are required, including Export Control policies & procedures. EAR and ITAR identified assets will be controlled strictly

  17. DEPARTMENT OF AGRICULTURAL ECONOMICS Faculty Tenure and Promotion Evaluation Procedures

    E-Print Network [OSTI]

    Behmer, Spencer T.

    DEPARTMENT OF AGRICULTURAL ECONOMICS Faculty Tenure and Promotion Evaluation Procedures Revised............................................20 2 #12;DEPARTMENT OF AGRICULTURAL ECONOMICS Faculty Tenure and Promotion Evaluation Procedures November 2013 #12;Table of Contents I. The Evaluation Process

  18. Portland State University Confidentiality and Information Management Policy and Procedures

    E-Print Network [OSTI]

    Bertini, Robert L.

    Portland State University Confidentiality and Information Management Policy and Procedures I and INFORMATION MANAGEMENT POLICY and PROCEDURES Confidentiality and Information Management Policy Information to in the rest of this document as "Confidential University Information." Database records, documents

  19. Measurement and Treatment of Nuisance Odors at Wastewater Treatment Plants

    E-Print Network [OSTI]

    Abraham, Samantha Margaret

    2014-01-01T23:59:59.000Z

    oil refineries, and waste treatment operations such as composting, sludgeoil refineries, and waste treatment operations such as composting, sludge

  20. On the Translation of Procedures to Finite Machines

    E-Print Network [OSTI]

    Müller-Olm, Markus

    On the Translation of Procedures to Finite Machines Abstraction Allows a Clean Proof Markus M¨uller-Olm

  1. On the Translation of Procedures to Finite Machines

    E-Print Network [OSTI]

    Müller-Olm, Markus

    On the Translation of Procedures to Finite Machines Abstraction Allows a Clean Proof Markus MË?uller­Olm

  2. Federal Energy Management Program Procedure for Notifying Congress...

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

    Document displays the Federal Energy Management Program's Procedure for notifying Congress prior to awarding energy savings performance contracts (ESPCs) espccongressionalnotific...

  3. Transthoracic Adrenal Biopsy Procedure Using Artificial Carbon Dioxide Pneumothorax as Outpatient Procedure

    SciTech Connect (OSTI)

    Favelier, Sylvain [CHU (University Hospital), Department of Radiology (France); Guiu, Severine [Georges-Francois Leclerc Cancer Center, Department of Oncology (France); Cherblanc, Violaine; Cercueil, Jean-Pierre; Krause, Denis; Guiu, Boris, E-mail: boris.guiu@chu-dijon.fr [CHU (University Hospital), Department of Radiology (France)

    2013-08-01T23:59:59.000Z

    Many routes have been described for percutaneous adrenal gland biopsy. They require either a complex non-axial path or a long hydrodissection or even pass through an organ thereby increasing complications. We describe here an approach using an artificially-induced carbon dioxide (CO{sub 2}) pneumothorax, performed as an outpatient procedure in a 57-year-old woman. Under local anaesthesia, 200 ml of CO{sub 2} was injected in the pleural space through a Veress needle under computed tomography fluoroscopy, to clear the lung parenchyma from the biopsy route. Using this technique, transthoracic adrenal biopsy can be performed under simple local anaesthesia as an safely outpatient procedure.

  4. The CIFF Proof Procedure for Abductive Logic Programming with Constraints

    E-Print Network [OSTI]

    Toni, Francesca

    The CIFF Proof Procedure for Abductive Logic Programming with Constraints U. Endriss1 , P,terreni,toni}@di.unipi.it Abstract. We introduce a new proof procedure for abductive logic pro- gramming and present two soundness results. Our procedure extends that of Fung and Kowalski by integrating abductive reasoning

  5. Cancellation or Refusal of Enrolment Procedure Student Policy Group

    E-Print Network [OSTI]

    Frean, Marcus

    this procedure is regarded as an extreme measure, and shall be taken only after careful consideration and Guidelines 4.1 Use of this procedure Cancelling an enrolment or refusing to permit an eligible person to enrol under this procedure is regarded as an extreme measure, and shall be taken only after careful

  6. ECU Physicians Group Practice Policy and Procedure Manual

    E-Print Network [OSTI]

    ECU Physicians Group Practice Policy and Procedure Manual Topic: Advance Care Planning - #C31 Planning practices. IV. Procedure: A. The Social Work and Case Management Department will insure Group Practice Policy and Procedure Manual Topic: Advance Care Planning - #C31 Section No. 2 Section

  7. Long-length contaminated equipment burial containers fabrication process procedures

    SciTech Connect (OSTI)

    McCormick, W.A., Fluor Daniel Hanford

    1997-03-11T23:59:59.000Z

    These special process procedures cover the detailed step-by-step procedures required by the supplier who will manufacture the Long-Length Contaminated Equipment (LLCE) Burial Container design. Also included are detailed step-by-step procedures required by the disposal process for completion of the LLCE Burial Containers at Hanford.

  8. Apollo 15 Contingency Procedures ATM-1003 7/10171

    E-Print Network [OSTI]

    Rathbun, Julie A.

    Reference: Addendum 1 Apollo 15 Contingency Procedures ATM-1003 7/10171 INO. ~9712-468 ' 1 Letter No. 9712-441 dated 7 I 9171 Contingency Procedures Apollo 15 Letter No. 9712-259 dated 3 I 27171 Review Copy, Contingency Procedures Apollo 15. As a result of recent activities involving Boydbolts for A

  9. Official University Facebook page guidelines and procedures -revised January 10, 2014 UL Lafayette Facebook Page Guidelines and Procedures

    E-Print Network [OSTI]

    Kearfott, R. Baker

    Official University Facebook page guidelines and procedures - revised January 1 UL Lafayette Facebook Page Guidelines and Procedures For all UL setting up a Facebook presence for any University entity, college, department

  10. Wesleyan Guest Wireless connection procedure. Please follow the procedure below for connecting to the Wesleyan Guest Wireless network.

    E-Print Network [OSTI]

    Devoto, Stephen H.

    for connecting to the Wesleyan Guest Wireless network. Begin by selecting the Wireless icon in the lower rightWesleyan Guest Wireless connection procedure. Windows #12;Please follow the procedure below

  11. Sampling and Analysis Plan - Waste Treatment Plant Seismic Boreholes Project

    SciTech Connect (OSTI)

    Reidel, Steve P.

    2006-05-26T23:59:59.000Z

    This sampling and analysis plan (SAP) describes planned data collection activities for four entry boreholes through the sediment overlying the basalt, up to three new deep rotary boreholes through the basalt and sedimentary interbeds, and one corehole through the basalt and sedimentary interbeds at the Waste Treatment Plant (WTP) site. The SAP will be used in concert with the quality assurance plan for the project to guide the procedure development and data collection activities needed to support borehole drilling, geophysical measurements, and sampling. This SAP identifies the American Society of Testing Materials standards, Hanford Site procedures, and other guidance to be followed for data collection activities.

  12. Factor water treatment up-front in IPP plant design

    SciTech Connect (OSTI)

    Levine, J.

    1994-09-01T23:59:59.000Z

    This article describes how independent power producers profit from drawing on the expertise of a water-treatment supplier at the inception of a project. Concepts presented here apply to other major subsystems. The nature of independent power project development, both domestic and international, has resulted in many innovative approaches to client service. The highly competitive, fast-track nature of project development requires that financial pro forma plans remain fluid, with periodic updates made as the project races from conceptual design through financial closing. Suppliers are continually called upon to provide insight and expertise to facilitate the project. Their expertise is also sought by organizations considering the purchase of an existing independent power producer (IPP) facility. Many foundation steps'' occur during early commercial development. Among these are: response to a request for proposals, power slates agreements, feasibility studies, site qualification, contract negotiation, host development, and steam sales agreements. As the project moves forward, development of comprehensive design and equipment specifications, equipment selection, and financial analysis are required. One aspect frequently overlooked because of the multitude of business and technical issues involved is the water supply. With public water supplies often inaccessible, it may be necessary to make use of a poor-quality source--such as effluent from publicly owned treatment works (POTWs), acid mine drainage, host-facility process discharge, landfill leachate, and produced water from oil fields. Even if surface water or groundwater is available, the quality and often the quantity may be unknown, or there may be no provisions for discharge of wastewater.

  13. Vehicle Rental Procedure Outline the procedure for renting motor pool vehicles at University of Michigan (U-M).

    E-Print Network [OSTI]

    Kirschner, Denise

    Vehicle Rental Procedure Objective Outline the procedure for renting motor pool vehicles at University of Michigan (U-M). Procedure 1. All policies pertaining to U-M vehicles also pertain to motor pool rental vehicles. 2. Motor pool vehicles can be reserved for a period of a few hours up to one year. 3

  14. Medical Management Treatment Manual

    E-Print Network [OSTI]

    Bezrukov, Sergey M.

    Medical Management Treatment Manual: A Clinical Guide for Researchers and Clinicians) This manual is an adaptation of: Medical Management Treatment Manual: A Clinical Research Guide for Medically, Maryland #12;Message to the Users of this Medical Management (MM) Manual from the Editors Background

  15. Policy on Student Grievance Procedures February 15, 2013 110.00 POLICY ON STUDENT GRIEVANCE PROCEDURES

    E-Print Network [OSTI]

    California at Santa Cruz, University of

    Policy on Student Grievance Procedures ­ February 15, 2013 110.00 POLICY ON STUDENT GRIEVANCE, portions of the state of California Education Code, and the University of California Policies Applying, or under the Student-Related Policy Applying to Nondiscrimination on the Basis of Sex (see Section 150

  16. WVDL PATHOLOGY SECTION-PROCEDURES AND FEES PROCEDURES WI Out-of-State

    E-Print Network [OSTI]

    digestion, incineration, and cremation are at additional cost (see below). OTHER PROCEDURES WI Out.00$ arrangements have been made. ANIMAL CARCASS DISPOSAL Madison Lab Incineration of carcasses 0.35/lb 0.53/lb Tissue digestion of carcasses 0.35/lb 0.53/lb Barron Lab Incineration of carcasses 0.50/lb 0.75/lb

  17. Accident Procedure Outline the procedures for accidents involving University of Michigan (U-M) vehicles.

    E-Print Network [OSTI]

    Kirschner, Denise

    owned by U-M are covered by the U-M self insurance program administered by Risk Management. Procedure 1. An accident is defined as any incident that causes damage to people or property. 2. In the event. 4. If the accident causes personal injury to the driver, occupants and/or pedestrian, contact Risk

  18. Model of Procedure Usage – Results from a Qualitative Study to Inform Design of Computer-Based Procedures

    SciTech Connect (OSTI)

    Johanna H Oxstrand; Katya L Le Blanc

    2012-07-01T23:59:59.000Z

    The nuclear industry is constantly trying to find ways to decrease the human error rate, especially the human errors associated with procedure use. As a step toward the goal of improving procedure use performance, researchers, together with the nuclear industry, have been looking at replacing the current paper-based procedures with computer-based procedure systems. The concept of computer-based procedures is not new by any means; however most research has focused on procedures used in the main control room. Procedures reviewed in these efforts are mainly emergency operating procedures and normal operating procedures. Based on lessons learned for these previous efforts we are now exploring a more unknown application for computer based procedures - field procedures, i.e. procedures used by nuclear equipment operators and maintenance technicians. The Idaho National Laboratory, the Institute for Energy Technology, and participants from the U.S. commercial nuclear industry are collaborating in an applied research effort with the objective of developing requirements and specifications for a computer-based procedure system to be used by field operators. The goal is to identify the types of human errors that can be mitigated by using computer-based procedures and how to best design the computer-based procedures to do this. The underlying philosophy in the research effort is “Stop – Start – Continue”, i.e. what features from the use of paper-based procedures should we not incorporate (Stop), what should we keep (Continue), and what new features or work processes should be added (Start). One step in identifying the Stop – Start – Continue was to conduct a baseline study where affordances related to the current usage of paper-based procedures were identified. The purpose of the study was to develop a model of paper based procedure use which will help to identify desirable features for computer based procedure prototypes. Affordances such as note taking, markups, sharing procedures between fellow coworkers, the use of multiple procedures at once, etc. were considered. The model describes which affordances associated with paper based procedures should be transferred to computer-based procedures as well as what features should not be incorporated. The model also provides a means to identify what new features not present in paper based procedures need to be added to the computer-based procedures to further enhance performance. The next step is to use the requirements and specifications to develop concepts and prototypes of computer-based procedures. User tests and other data collection efforts will be conducted to ensure that the real issues with field procedures and their usage are being addressed and solved in the best manner possible. This paper describes the baseline study, the construction of the model of procedure use, and the requirements and specifications for computer-based procedures that were developed based on the model. It also addresses how the model and the insights gained from it were used to develop concepts and prototypes for computer based procedures.

  19. Evaluation of the computerized procedures Manual II (COPMA II)

    SciTech Connect (OSTI)

    Converse, S.A. [North Carolina State Univ., Raleigh, NC (United States)

    1995-11-01T23:59:59.000Z

    The purpose of this study was to evaluate the effects of a computerized procedure system, the Computerized Procedure Manual II (COPMA-II), on the performance and mental workload of licensed reactor operators. To evaluate COPMA-II, eight teams of two operators were trained to operate a scaled pressurized water reactor facility (SPWRF) with traditional paper procedures and with COPMA-II. Following training, each team operated the SPWRF under normal operating conditions with both paper procedures and COPMA-II. The teams then performed one of two accident scenarios with paper procedures, but performed the remaining accident scenario with COPMA-II. Performance measures and subjective estimates of mental workload were recorded for each performance trial. The most important finding of the study was that the operators committed only half as many errors during the accident scenarios with COPMA-II as they committed with paper procedures. However, time to initiate a procedure was fastest for paper procedures for accident scenario trials. For performance under normal operating conditions, there was no difference in time to initiate or to complete a procedure, or in the number of errors committed with paper procedures and with COPMA-II. There were no consistent differences in the mental workload ratings operators recorded for trials with paper procedures and COPMA-II.

  20. Robust estimation procedure in panel data model

    SciTech Connect (OSTI)

    Shariff, Nurul Sima Mohamad [Faculty of Science of Technology, Universiti Sains Islam Malaysia (USIM), 71800, Nilai, Negeri Sembilan (Malaysia); Hamzah, Nor Aishah [Institute of Mathematical Sciences, Universiti Malaya, 50630, Kuala Lumpur (Malaysia)

    2014-06-19T23:59:59.000Z

    The panel data modeling has received a great attention in econometric research recently. This is due to the availability of data sources and the interest to study cross sections of individuals observed over time. However, the problems may arise in modeling the panel in the presence of cross sectional dependence and outliers. Even though there are few methods that take into consideration the presence of cross sectional dependence in the panel, the methods may provide inconsistent parameter estimates and inferences when outliers occur in the panel. As such, an alternative method that is robust to outliers and cross sectional dependence is introduced in this paper. The properties and construction of the confidence interval for the parameter estimates are also considered in this paper. The robustness of the procedure is investigated and comparisons are made to the existing method via simulation studies. Our results have shown that robust approach is able to produce an accurate and reliable parameter estimates under the condition considered.