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Note: This page contains sample records for the topic "treatment procedure qualification" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
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1

Heat Treatment Procedure Qualification for Steel Castings  

SciTech Connect (OSTI)

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

Professor Robert C. Voigt

2003-02-02T23:59:59.000Z

2

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

SciTech Connect (OSTI)

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

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

2003-07-01T23:59:59.000Z

3

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

SciTech Connect (OSTI)

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

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

2013-07-01T23:59:59.000Z

4

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

SciTech Connect (OSTI)

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

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

1994-12-31T23:59:59.000Z

5

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

SciTech Connect (OSTI)

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

Herman, Connie C.

2013-09-30T23:59:59.000Z

6

Protective Force Firearms Qualification Courses  

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

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

7

Assessor Training Assessor Qualification &  

E-Print Network [OSTI]

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

8

On-Site Wastewater Treatment Systems: Soil Particle Analysis Procedure  

E-Print Network [OSTI]

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...

Lesikar, Bruce J.

2005-08-18T23:59:59.000Z

9

NORESCO ESCO Qualification Sheet  

Broader source: Energy.gov [DOE]

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

10

Firearms Qualification Courses Manual  

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

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

2002-01-17T23:59:59.000Z

11

BEREA COLLEGE VENDOR QUALIFICATION FORM  

E-Print Network [OSTI]

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

Baltisberger, Jay H.

12

AGR-1 Data Qualification Report  

SciTech Connect (OSTI)

ABSTRACT Projects for the very high temperature reactor (VHTR) Technology Development Office (TDO) program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program has established the NGNP Data Management and Analysis System (NDMAS) to ensure that VHTR data are (1) qualified for use, (2) stored in a readily accessible electronic form, and (3) analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the data streams associated with the first Advanced Gas Reactor experiment (AGR-1), the processing of these data within NDMAS, and reports the qualification status of the data. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category assigned by the data generator. They include: (1) capture testing, to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing, to confirm that the data are an accurate representation of the system or object being measured, and (3) documentation that the data were collected under an NQA-1 or equivalent quality assurance program. The NDMAS database processing and qualification status of the following five data streams is reported in this document: 1. Fuel fabrication data. All data have been processed into the NDMAS database and qualified (1,819 records). 2. Fuel irradiation data. Data from all 13 AGR-1 reactor cycles have been processed into the NDMAS database and tested. Of these, 85% have been qualified and 15% have failed NDMAS accuracy testing. 3. FPMS data. Reprocessed (January 2010) data from all 13 AGR-1 reactor cycles have been processed into the database and capture tested. Final qualification of these data will be recorded after QA approval of an Engineering Calculations and Analysis Report currently in review. 4. ATR Operating Conditions Data. Data for all AGR-1 cycles have been stored and capture tested. These data, which come from outside the VHTR program, are assumed to be qualified by ATR quality control procedures. 5. Neutronics and Thermal Modeling Data. NDMAS processing is in progress. These data will not be qualified by NDMAS.

Michael Abbott

2010-03-01T23:59:59.000Z

13

Firearms Qualification Courses Manual  

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

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

1997-08-21T23:59:59.000Z

14

Business Case for Technical Qualification Program Accreditation...  

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

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

15

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

SciTech Connect (OSTI)

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

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

2012-05-16T23:59:59.000Z

16

Qualification Status List (QSL Package)  

E-Print Network [OSTI]

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

Rathbun, Julie A.

17

Firearms Qualification Courses Manual  

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

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

1997-07-08T23:59:59.000Z

18

Firearms Qualification Courses Manual  

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

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

1992-12-01T23:59:59.000Z

19

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).

20

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).

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


21

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...

22

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).

23

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).

24

Experience gained from equipment qualification inspections  

SciTech Connect (OSTI)

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

Jacobus, M.J.

1986-01-01T23:59:59.000Z

25

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.

26

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.

27

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

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

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

28

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.

29

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.

30

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.

31

FAQS Qualification Card Criticality Safety  

Broader source: Energy.gov [DOE]

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

32

FAQS Qualification Card- Aviation Manager  

Broader source: Energy.gov [DOE]

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

33

FAQS Qualification Card Environment Compliance  

Broader source: Energy.gov [DOE]

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

34

FAQS Qualification Card Environmental Restoration  

Broader source: Energy.gov [DOE]

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

35

FAQS Qualification Card Waste Management  

Broader source: Energy.gov [DOE]

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

36

FAQS Qualification Card- Construction Management  

Broader source: Energy.gov [DOE]

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

37

SRNL PHASE 1 ASSESSMENT OF THE WTP WASTE QUALIFICATION PROGRAM  

SciTech Connect (OSTI)

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

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

2012-03-06T23:59:59.000Z

38

Issues in the flight qualification of a space power reactor  

SciTech Connect (OSTI)

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

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

1994-10-01T23:59:59.000Z

39

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

Office of Environmental Management (EM)

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

40

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

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

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

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


41

ITER CENTRAL SOLENOID COIL INSULATION QUALIFICATION  

SciTech Connect (OSTI)

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

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

2009-06-11T23:59:59.000Z

42

ITER Central Solenoid Coil Insulation Qualification  

SciTech Connect (OSTI)

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

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

2010-01-01T23:59:59.000Z

43

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).

44

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

SciTech Connect (OSTI)

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

Not Available

1980-01-01T23:59:59.000Z

45

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

SciTech Connect (OSTI)

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

Cook, J.F.

1987-10-01T23:59:59.000Z

46

CONSIDERATIONS FOR THE TREATMENT OF COMPUTERIZED PROCEDURES IN HUMAN RELIABILITY ANALYSIS  

SciTech Connect (OSTI)

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.

Ronald L. Boring; David I. Gertman

2012-07-01T23:59:59.000Z

47

Optimization Online - Constraint Qualification Failure in Second ...  

E-Print Network [OSTI]

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

Hassan L. Hijazi

2014-07-22T23:59:59.000Z

48

Committee on Educational Policy MAJOR QUALIFICATION POLICY  

E-Print Network [OSTI]

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

California at Santa Cruz, University of

49

Contract PQQ Pre-Qualification  

E-Print Network [OSTI]

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

50

Analysis of Patient Treatment Procedures R.P. Jagadeesh Chandra Bose1,2  

E-Print Network [OSTI]

a Dutch Academic Hos- pital, provided for the BPI challenge is analyzed using process mining techniques. The log contains events related to treatment and diagnosis steps for patients diagnosed with cancer. Given subsets of cases (e.g., patients having a particular type of cancer that need to be treated urgently

van der Aalst, Wil

51

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

SciTech Connect (OSTI)

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.

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

2002-09-30T23:59:59.000Z

52

FPL Energy Services ESCO Qualification Sheet  

Broader source: Energy.gov [DOE]

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

53

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).

54

History of IEC Qualification Standards (Presentation)  

SciTech Connect (OSTI)

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

Wohlhgemuth, J.

2011-07-01T23:59:59.000Z

55

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).

56

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

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

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

57

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

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

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

58

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.

59

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.

60

FAQS Qualification Card Fire Protection Engineering  

Broader source: Energy.gov [DOE]

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

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


61

FAQS Qualification Card Nuclear Explosive Safety Study  

Broader source: Energy.gov [DOE]

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

62

FAQS Qualification Card- Aviation Safety Officer  

Broader source: Energy.gov [DOE]

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

63

FAQS Qualification Card Facility Maintenance Management  

Broader source: Energy.gov [DOE]

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

64

FAQS Qualification Card Senior Technical Safety Manager  

Broader source: Energy.gov [DOE]

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

65

FAQS Qualification Card Safeguards and Security  

Broader source: Energy.gov [DOE]

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

66

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).

67

Seismic equipment qualification at Rocky Flats Plant: Lessons learned  

SciTech Connect (OSTI)

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

Peregoy, W.; Herring, K.

1993-08-01T23:59:59.000Z

68

Qualification tests for {sup 192}Ir sealed sources  

SciTech Connect (OSTI)

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

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

2013-12-16T23:59:59.000Z

69

Changing nature of equipment and parts qualification  

SciTech Connect (OSTI)

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

Bucci, R.M.

1988-01-01T23:59:59.000Z

70

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

E-Print Network [OSTI]

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

Rubloff, Gary W.

71

AGC-2 Irradiation Data Qualification Final Report  

SciTech Connect (OSTI)

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

Laurence C. Hull

2012-07-01T23:59:59.000Z

72

Achieving agility through parameter space qualification  

SciTech Connect (OSTI)

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

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

1995-02-01T23:59:59.000Z

73

AGR-1 Data Qualification Interim Report  

SciTech Connect (OSTI)

Projects for the very-high-temperature reactor (VHTR) program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR Program has established the NGNP Data Management and Analysis System (NDMAS) to ensure that VHTR data are (1) qualified for use, (2) stored in a readily accessible electronic form, and (3) analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the data streams associated with the first Advanced Gas Reactor (AGR-1) experiment, the processing of these data within NDMAS, and reports the interim FY09 qualification status of the AGR-1 data to date. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category, which is assigned by the data generator, and include: (1) capture testing, to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing, to confirm that the data are an accurate representation of the system or object being measured, and (3) documentation that the data were collected under an NQA-1 or equivalent QA program. The interim qualification status of the following four data streams is reported in this document: (1) fuel fabrication data, (2) fuel irradiation data, (3) fission product monitoring system (FPMS) data, and (4) Advanced Test Reactor (ATR) operating conditions data. A final report giving the NDMAS qualification status of all AGR-1 data (including cycle 145A) is planned for February 2010.

Machael Abbott

2009-08-01T23:59:59.000Z

74

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

SciTech Connect (OSTI)

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

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

2000-08-23T23:59:59.000Z

75

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

SciTech Connect (OSTI)

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.

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

2001-10-30T23:59:59.000Z

76

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

SciTech Connect (OSTI)

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

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

1996-12-31T23:59:59.000Z

77

Safety critical software development qualification  

SciTech Connect (OSTI)

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

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

2006-07-01T23:59:59.000Z

78

RERTR Fuel Developmemt and Qualification Plan  

SciTech Connect (OSTI)

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

Dan Wachs

2007-01-01T23:59:59.000Z

79

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

SciTech Connect (OSTI)

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

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

2013-04-01T23:59:59.000Z

80

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 Sacramentos 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.

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


81

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

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

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

82

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...

83

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...

84

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

SciTech Connect (OSTI)

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

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

2013-01-25T23:59:59.000Z

85

Safety Management Manual Safety Management Procedures  

E-Print Network [OSTI]

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

Kurapov, Alexander

86

Department for Education Assessment, Curriculum and General Qualifications  

E-Print Network [OSTI]

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

Rambaut, Andrew

87

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

SciTech Connect (OSTI)

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

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

2014-03-01T23:59:59.000Z

88

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

SciTech Connect (OSTI)

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

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

1980-01-01T23:59:59.000Z

89

FAQS Qualification Card Safeguards and Security General Technical Base  

Broader source: Energy.gov [DOE]

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

90

Large Bore Powder Gun Qualification (U)  

SciTech Connect (OSTI)

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

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

2012-04-02T23:59:59.000Z

91

High-level waste qualification: Managing uncertainty  

SciTech Connect (OSTI)

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

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

1993-12-31T23:59:59.000Z

92

Qualifications | Y-12 National Security Complex  

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

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

93

Confinement Ventilation and Process Gas Treatment Functional Area Qualification Standard  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-Up fromDepartmentTieCelebrate Earth Codestheatfor Optimized91 * SeptemberUS Department

94

Equipment qualification issues research and resolution: Status report  

SciTech Connect (OSTI)

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

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

1986-11-01T23:59:59.000Z

95

Staubli TX-90XL robot qualification at the LLIHE.  

SciTech Connect (OSTI)

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

Covert, Timothy Todd

2010-10-01T23:59:59.000Z

96

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...

97

ASSESSMENT OF SRSO TRAINING & QUALIFICATION PROGRAM  

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

systems, processes and procedures are in place to develop, monitormaintain and evaluate organizational and individual's performance. Systems such as PAMS and CHRIS are enabling...

98

Secondary Waste Cast Stone Waste Form Qualification Testing Plan  

SciTech Connect (OSTI)

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

Westsik, Joseph H.; Serne, R. Jeffrey

2012-09-26T23:59:59.000Z

99

Workshop on environmental qualification of electric equipment  

SciTech Connect (OSTI)

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

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

1994-05-01T23:59:59.000Z

100

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

SciTech Connect (OSTI)

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

Muller, M.

2012-03-01T23:59:59.000Z

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


101

AGC-3 Irradiation Data Qualification Final Report  

SciTech Connect (OSTI)

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

Laurence Hull

2014-08-01T23:59:59.000Z

102

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

SciTech Connect (OSTI)

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

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

2000-06-09T23:59:59.000Z

103

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

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

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

2001-07-12T23:59:59.000Z

104

Decant pump assembly and controls qualification testing - test report  

SciTech Connect (OSTI)

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

Staehr, T.W., Westinghouse Hanford

1996-05-02T23:59:59.000Z

105

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

SciTech Connect (OSTI)

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

Edwards, T; Mahannah, R.

2011-07-05T23:59:59.000Z

106

Code qualification of structural materials for AFCI advanced recycling reactors.  

SciTech Connect (OSTI)

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

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

2012-05-31T23:59:59.000Z

107

Training and Qualification Program at the Saturn Facility  

SciTech Connect (OSTI)

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

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

1993-01-01T23:59:59.000Z

108

Training and Qualification Program at the Simulation Technology Laboratory  

SciTech Connect (OSTI)

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

Zawadzkas, G.A.

1992-03-01T23:59:59.000Z

109

High Temperature Materials Interim Data Qualification Report FY 2011  

SciTech Connect (OSTI)

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

Nancy Lybeck

2011-08-01T23:59:59.000Z

110

Plutonium metal and oxide container weld development and qualification  

SciTech Connect (OSTI)

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

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

1996-01-01T23:59:59.000Z

111

AGR-2 Data Qualification Report for ATR Cycle 154B  

SciTech Connect (OSTI)

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

Binh Pham; Jeff Einerson

2014-01-01T23:59:59.000Z

112

Qualification of NDE personnel in the nuclear industry  

SciTech Connect (OSTI)

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

Epps, T.N.

1984-06-01T23:59:59.000Z

113

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

E-Print Network [OSTI]

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

Glasgow, University of

114

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).

115

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.

116

Qualification tests of materials for spallation neutron sources  

SciTech Connect (OSTI)

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

Sommer, W.F.

1996-12-31T23:59:59.000Z

117

FAQS Qualification Card - Mechanical Systems | Department of Energy  

Energy Savers [EERE]

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

118

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

SciTech Connect (OSTI)

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

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

2014-06-01T23:59:59.000Z

119

DOT-7A Type A packaging test and evaluation procedure  

SciTech Connect (OSTI)

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).

Kelly, D.L., Westinghouse Hanford

1996-06-13T23:59:59.000Z

120

Delegation Procedures - DOE Directives, Delegations, and Requirements  

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

Delegation Procedures Text Delegation Procedures Delegation Template Text Redelegation Procedures Redelegation Template Delegation Procedures Redelegation Procedures...

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


121

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

SciTech Connect (OSTI)

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

SAMS TL; EDGE JA; SWANBERG DJ; ROBBINS RA

2011-01-13T23:59:59.000Z

122

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

SciTech Connect (OSTI)

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

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

2011-06-01T23:59:59.000Z

123

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 ......

124

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

SciTech Connect (OSTI)

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

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

1996-12-01T23:59:59.000Z

125

EDS V25 containment vessel explosive qualification test report.  

SciTech Connect (OSTI)

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

Rudolphi, John Joseph

2012-04-01T23:59:59.000Z

126

Contract and Procedure  

E-Print Network [OSTI]

This paper examines both the theoretical underpinnings and empirical picture of procedural contracts. Procedural contracts may be understood as contracts in which parties regulate not merely their commercial relations but also the procedures...

Drahozal, Christopher R.

2011-01-01T23:59:59.000Z

127

Student Policies & Procedures  

E-Print Network [OSTI]

Student Policies & Procedures summer.uci.edu #12;STUDENT POLICIES AND PROCEDURES Rev. 04/2014 1 ...................................................................................... 9 #12;STUDENT POLICIES AND PROCEDURES Rev. 04/2014 2 Who Summer Session Serves Current UCI Students

Barrett, Jeffrey A.

128

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.

129

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

Broader source: Energy.gov [DOE]

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

130

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.

131

"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,...

132

Fuel qualification plan for the Advanced Neutron Source Reactor  

SciTech Connect (OSTI)

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

Copeland, G.L.

1995-07-01T23:59:59.000Z

133

Technology transfer equipment qualification methodology for shelf life determination  

SciTech Connect (OSTI)

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

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

1995-08-01T23:59:59.000Z

134

Centralized maintenance procedures  

SciTech Connect (OSTI)

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.

Barber, J.R.

1994-02-01T23:59:59.000Z

135

Computerized procedures system  

SciTech Connect (OSTI)

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.

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

2010-10-12T23:59:59.000Z

136

Implementing MSE 2000: Procedures  

E-Print Network [OSTI]

do not spawn lasting procedures, and the advances achieved through crisis management are not sustained without formal procedures and an organizational commitment to continual improvement, efficiency gains made during an energy dilemma are quickly lost...

Brown, M.; Adams, J.

137

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...

138

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

SciTech Connect (OSTI)

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

Peters, T. B.

2013-02-26T23:59:59.000Z

139

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

SciTech Connect (OSTI)

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

NONE

1996-03-01T23:59:59.000Z

140

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

SciTech Connect (OSTI)

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

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

1998-01-01T23:59:59.000Z

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


141

Non-destructive qualification tests for ITER cryogenic axial insulating breaks  

SciTech Connect (OSTI)

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

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

2014-01-29T23:59:59.000Z

142

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

E-Print Network [OSTI]

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

American Society for Testing and Materials. Philadelphia

2007-01-01T23:59:59.000Z

143

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

SciTech Connect (OSTI)

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

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

2011-03-14T23:59:59.000Z

144

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

SciTech Connect (OSTI)

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

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

2014-06-01T23:59:59.000Z

145

Cable Measuring Engine Operation Procedures  

E-Print Network [OSTI]

MEASURING ENGINE OPERATION PROCEDURES LBNL-40565 SC-MAG-597MEASURING ENGINE OPERATION PROCEDURES INDEX IN T ROD U C TCALIBRATION PROCEDURE . .

Authors, Various

2011-01-01T23:59:59.000Z

146

Qualification test for the flexible receiver. Revision 2  

SciTech Connect (OSTI)

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.

Tedeschi, D.J.

1994-12-12T23:59:59.000Z

147

PROCEDURES FOR ARC PROJECTS  

E-Print Network [OSTI]

PROCEDURES FOR ARC PROJECTS Revised - May 2013 Agricultural Research Center Washington State University #12;Table of Contents THE PROJECT SYSTEM, AN INTRODUCTION................................................................................. 5 DEVELOPING AN ARC PROJECT

Collins, Gary S.

148

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.

149

Teaching Physician Guidelines for Surgical Procedures Minor Surgical Procedures  

E-Print Network [OSTI]

Teaching Physician Guidelines for Surgical Procedures Minor Surgical Procedures: § Procedures, the teaching physician must be present for the entire procedure § Teaching physician or resident may document the teaching physician's presence for the entire procedure High Risk and Complex Surgical Procedures

Goldman, Steven A.

150

Model Request for Qualifications to Pre-Qualify Energy Service Companies  

Broader source: Energy.gov [DOE]

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

151

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

E-Print Network [OSTI]

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

Walker, Matthew P.

152

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.

153

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

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

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

2010-04-21T23:59:59.000Z

154

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

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

The order establishes selection, training, qualification, and certification requirements for contractor personnel who can impact the safety basis through their involvement in the operation, maintenance, and technical support of Hazard Category 1, 2, and 3 nuclear facilities. Cancels DOE O 5480.20A. Admin Chg 1, dated 7-29-13, cancels DOE O 426.2.

2010-04-21T23:59:59.000Z

155

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

SciTech Connect (OSTI)

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

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

2012-12-20T23:59:59.000Z

156

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

SciTech Connect (OSTI)

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

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

2012-12-11T23:59:59.000Z

157

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

E-Print Network [OSTI]

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

Rathbun, Julie A.

158

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.

159

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

E-Print Network [OSTI]

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

Rivest, Ronald L.

160

Procedures in Modules (1) Including all procedures within modules  

E-Print Network [OSTI]

Procedures in Modules (1) Including all procedures within modules works very well in almost all designing these if possible #12;Procedures in Modules (2) These are very much like internal procedures Works very well in almost all programs Everything accessible in the module can also be used in the procedure

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


161

EML procedures manual  

SciTech Connect (OSTI)

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.

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

1982-01-01T23:59:59.000Z

162

Quiz Policies and Procedures  

E-Print Network [OSTI]

Quiz Policies and Procedures. 1. Studying the lesson notes and completing most of the homework problems prior to class is the best way to prepare for a quiz. 2.

Bailey, Charlotte M

2014-08-19T23:59:59.000Z

163

Statistical simulation procedures  

E-Print Network [OSTI]

. Ringer This thesis investicates methods for estimating statistical distribution functions which cannot be easily solved by theoretical techniques. The stratified Ilonte Carlo procedure of Ringer and Suharto [11j is extended to the multivariate case... and applied to two probIems, one practical, the other theoretical. This procedure Is shown to be more precise than simple Monte Carlo simula- t. i on. numerical method proposed by Soserville [12j is also extended to the multivariate case, and compared...

Tremelling, Robert Norman

2012-06-07T23:59:59.000Z

164

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

SciTech Connect (OSTI)

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

Wohlgemuth, J. H.; Kurtz, S.

2011-02-01T23:59:59.000Z

165

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

SciTech Connect (OSTI)

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

Peeler, D.

2013-06-27T23:59:59.000Z

166

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

SciTech Connect (OSTI)

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

NONE

1996-03-01T23:59:59.000Z

167

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

SciTech Connect (OSTI)

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

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

2013-09-25T23:59:59.000Z

168

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

SciTech Connect (OSTI)

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

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

1995-12-31T23:59:59.000Z

169

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.

170

Mobile Energy Laboratory Procedures  

SciTech Connect (OSTI)

Pacific Northwest Laboratory (PNL) has been tasked to plan and implement a framework for measuring and analyzing the efficiency of on-site energy conversion, distribution, and end-use application on federal facilities as part of its overall technical support to the US Department of Energy (DOE) Federal Energy Management Program (FEMP). The Mobile Energy Laboratory (MEL) Procedures establish guidelines for specific activities performed by PNL staff. PNL provided sophisticated energy monitoring, auditing, and analysis equipment for on-site evaluation of energy use efficiency. Specially trained engineers and technicians were provided to conduct tests in a safe and efficient manner with the assistance of host facility staff and contractors. Reports were produced to describe test procedures, results, and suggested courses of action. These reports may be used to justify changes in operating procedures, maintenance efforts, system designs, or energy-using equipment. The MEL capabilities can subsequently be used to assess the results of energy conservation projects. These procedures recognize the need for centralized NM administration, test procedure development, operator training, and technical oversight. This need is evidenced by increasing requests fbr MEL use and the economies available by having trained, full-time MEL operators and near continuous MEL operation. DOE will assign new equipment and upgrade existing equipment as new capabilities are developed. The equipment and trained technicians will be made available to federal agencies that provide funding for the direct costs associated with MEL use.

Armstrong, P.R.; Batishko, C.R.; Dittmer, A.L.; Hadley, D.L.; Stoops, J.L.

1993-09-01T23:59:59.000Z

171

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

SciTech Connect (OSTI)

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

NONE

1996-03-01T23:59:59.000Z

172

Evidence in European Asylum Procedures.  

E-Print Network [OSTI]

??This thesis explores the particular framework of evidentiary assessment of three selected appellate national asylum procedures in Europe and discusses the relationship between these procedures, (more)

Staffans, Ida

2011-01-01T23:59:59.000Z

173

Emergency Procedures | Department of Energy  

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

Services Employee Services Safety and Health Emergency Procedures Emergency Procedures Note: This page is pending deletion, please refer to the Safety and health main page...

174

Policy Procedure Administrative Directive Title: _____________________________________  

E-Print Network [OSTI]

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

Northern British Columbia, University of

175

Cable Measuring Engine Operation Procedures  

E-Print Network [OSTI]

gov CABLE MEASURING ENGINE OPERATION PROCEDURES LBNL-40565LBNL-40565 CABLE MEASURING ENGINE OPERATION PROCEDURES INDEXThe Cable Measuring Engine (CME) is a tool which measures

Authors, Various

2011-01-01T23:59:59.000Z

176

ACADEMIC PROGRAM PROCEDURE MANUAL  

E-Print Network [OSTI]

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

Fay, Noah

177

PHYSICAL PLANT POLICY & PROCEDURE  

E-Print Network [OSTI]

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

Fernandez, Eduardo

178

HASL procedures manual  

SciTech Connect (OSTI)

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)

Not Available

1980-08-01T23:59:59.000Z

179

Building Programming List Procedures  

E-Print Network [OSTI]

1 6.090 Building Programming Experience Lecture 4 1/16/2007 Outline · List Procedures · Compound)) (define (reverse-helper l r) (if (null? l) r (reverse-helper (cdr l) (cons (car l) r)))) list-ref · Write

180

EMERGENCY PROCEDURES --2013 INFORMATION  

E-Print Network [OSTI]

quickly, remain calm. Take personal items (keys, purse, wallet, coat, shoes) Secure any hazardous procedures. SHOOTING INCIDENT If shooter is outside building: Turn off lights, lock windows and doors, close police. If shooter is inside the building: If safe to exit, flee. Call 9-1-1 to give location. Do

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


181

EMERGENCY PROCEDURES --2014 INFORMATION  

E-Print Network [OSTI]

hazardous materials. Close door when you exit. Go to evacuation assembly point designated by evacu- ation procedures. SHOOTING INCIDENT If shooter is outside building: Turn off lights, lock windows and doors, close of uniformed police. If shooter is inside the building: If safe to exit, flee. Call 9-1-1 to give location

182

Appendix A: STANDARD OPERATING PROCEDURES  

E-Print Network [OSTI]

1 Appendix A: STANDARD OPERATING PROCEDURES A. STANDARD OPERATING PROCEDURES Standard Operating Procedures (SOP) are written safety and health guidelines for laboratory work with hazardous chemicals Procedures be written for hazardous chemicals when the chemical is used routinely in the laboratory and when

Ferrara, Katherine W.

183

Pollutant Assessments Group Procedures Manual  

SciTech Connect (OSTI)

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.

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

184

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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc Documentation RUC :ProductsSCM Forcing Data Derived fromgovPublicationsPublications Procedures

185

SLUDGE BATCH 7B QUALIFICATION ACTIVITIES WITH SRS TANK FARM SLUDGE  

SciTech Connect (OSTI)

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

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

2011-11-16T23:59:59.000Z

186

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

SciTech Connect (OSTI)

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

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

1994-04-01T23:59:59.000Z

187

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

SciTech Connect (OSTI)

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

McCoskey, Jacob K.

2014-01-22T23:59:59.000Z

188

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

SciTech Connect (OSTI)

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

Oji, L. N.

2013-03-07T23:59:59.000Z

189

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

SciTech Connect (OSTI)

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

Peters, T.; Fink, S.

2012-03-26T23:59:59.000Z

190

Quality Assurance Program Plan for AGR Fuel Development and Qualification Program  

SciTech Connect (OSTI)

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

W. Ken Sowder

2004-02-01T23:59:59.000Z

191

Energy Metering Audit Procedure  

E-Print Network [OSTI]

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..., cx:ndensate, natural gas, water, nitrogen and air flCMS to the different process units within the plant. This audit started as an attellPt to resolve discrepan::ies between the 650 PSIG steam distriootion and supply meters. Theoretically the sum...

Whitaker, W. S.

192

Surface cleanliness measurement procedure  

DOE Patents [OSTI]

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.

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

2002-01-01T23:59:59.000Z

193

PROCEDURE FOR PREPARING  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power.pdf11-161-LNG |September 15, 2010Energy6 Frontera GenerationMedicine -PROCEDURE FOR

194

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

SciTech Connect (OSTI)

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

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

2002-02-25T23:59:59.000Z

195

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

E-Print Network [OSTI]

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

Hochberg, Michael

196

Motor Vehicle Record Procedure Objective  

E-Print Network [OSTI]

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

Kirschner, Denise

197

Shrinking Procedures and Optimal Algorithms  

E-Print Network [OSTI]

Jun 18, 2012 ... Optimal Stochastic Approximation Algorithms for Strongly Convex Stochastic Composite Optimization, II: Shrinking Procedures and Optimal...

Saeed Ghadimi

2012-06-18T23:59:59.000Z

198

Princeton Plasma Physics Laboratory D-SITE Procedure  

E-Print Network [OSTI]

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

Princeton Plasma Physics Laboratory

199

Handbook of Academic Requirements & Procedures  

E-Print Network [OSTI]

Handbook of Academic Requirements & Procedures for the Chemistry/Biotechnology Graduate Program. A detailed account of the academic requirements and procedures is provided for graduate students in chemistry; to promote consistency in procedures and standards; and to provide a basis for communication between

Kounaves, Samuel P.

200

Postgraduate Admissions Policy and Procedures  

E-Print Network [OSTI]

1 Postgraduate Admissions Policy and Procedures SCOPE OF POLICY This policy applies to all to both staff and applicants on the University's procedures for admitting postgraduate students PROCEDURES 5 3.1 Making an application 5 3.2 Application deadlines 5 3.3 Accreditation of Prior Learning (APL

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


201

PROCEDURES FOR THE APPOINTMENT AND  

E-Print Network [OSTI]

1 PROCEDURES FOR THE APPOINTMENT AND RE-APPOINTMENT OF THE UNIVERSITY LIBRARIAN University Policy PURPOSE 1.00 The following procedures define the method by which the appointment, or review and re-appointment, of the university librarian will be conducted. SCOPE 2.00 These procedures apply to: the appointment of a new

Victoria, University of

202

PROCEDURES FOR THE APPOINTMENT AND  

E-Print Network [OSTI]

Page | 1 PROCEDURES FOR THE APPOINTMENT AND RE-APPOINTMENT OF ACADEMIC ASSOCIATE VICE Review: February, 2018 PURPOSE 1.00 The following procedures define the method by which the appointment.00 These procedures apply to the appointment and reappointment of academic Associate Vice-Presidents. An Academic

Victoria, University of

203

PROCEDURES FOR THE APPOINTMENT AND  

E-Print Network [OSTI]

Page | 1 PROCEDURES FOR THE APPOINTMENT AND RE-APPOINTMENT OF DEANS University Policy No: GV0450 procedures define the method by which the appointment, or review and re-appointment, of deans will be conducted. SCOPE 2.00 These procedures apply to: the appointments of new deans, the review and re

Victoria, University of

204

Handbook of Academic Requirements & Procedures  

E-Print Network [OSTI]

Handbook of Academic Requirements & Procedures for the Chemistry Graduate Program PLEASE NOTE and procedures is provided. The intent is to describe the programs and explain the rationale behind them of the Department; to promote consistency in procedures and standards; and to provide a basis for communication

Kounaves, Samuel P.

205

PROCEDURES FOR THE APPOINTMENT AND  

E-Print Network [OSTI]

Page 1 PROCEDURES FOR THE APPOINTMENT AND RE-APPOINTMENT OF THE ASSOCIATE DEAN ACADEMIC ADVISING Last Editorial Change: Mandated Review: May, 2018 PURPOSE 1.00 The following procedures define (Faculties of Science, Social Sciences and Humanities) will be conducted. SCOPE 2.00 These procedures apply

Victoria, University of

206

Capital Projects Delivery Procedures Manual  

E-Print Network [OSTI]

1 Capital Projects Delivery Procedures Manual September 4, 2008 Office of the CFO #12;2 Page I of the Capital Budget 11 B. Budget Approval 12 C. Setting Up Capital Projects 13 III. Procedures for Design ­ Office of the Chief Financial Officer Financial Policies and Procedures for the Capital Project Delivery

Alpay, S. Pamir

207

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)

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.

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

208

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)

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.

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

209

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

SciTech Connect (OSTI)

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

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

2012-08-01T23:59:59.000Z

210

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

SciTech Connect (OSTI)

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

NONE

1993-02-01T23:59:59.000Z

211

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

SciTech Connect (OSTI)

The DOE Guide to Good Practices For The Selection, Training, and Qualification of Shift Technical Advisors can be used by any DOE nuclear facility that has implemented the shift technical advisor position. DOE Order 5480-20, ``Personnel Selection, Qualification, Training, and Staffing Requirements at DOE Reactor and Non-Reactor Nuclear Facilities,`` states that only Category A reactors must use shift technical advisor position. However, many DOE nuclear facilities have implemented the shift technical advisor position to provide independent on-shift technical advice and counsel to the shift operating personnel to help determine cause and mitigation of facility accidents. Those DOE nuclear facilities that have implemented or are going to implement the shift technical advisor position will find this guide useful. This guide addresses areas that may be covered by other training programs. In these cases, it is unnecessary (and undesirable) to duplicate these areas in the STA training program as long as the specific skills and knowledge essential for STAs are addressed. The guide is presented based on the premise that the trainee has not completed any facility-specific training other than general employee training.

Not Available

1993-02-01T23:59:59.000Z

212

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

SciTech Connect (OSTI)

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

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

2013-08-01T23:59:59.000Z

213

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

SciTech Connect (OSTI)

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

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

2012-08-01T23:59:59.000Z

214

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

E-Print Network [OSTI]

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

Utrecht, Universiteit

215

Safe Operating Procedure (Revised 7/11)  

E-Print Network [OSTI]

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

Farritor, Shane

216

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

E-Print Network [OSTI]

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

Rambaut, Andrew

217

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

SciTech Connect (OSTI)

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

Edwards, T.; Mahannah, R.

2011-07-05T23:59:59.000Z

218

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

SciTech Connect (OSTI)

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

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

2005-09-30T23:59:59.000Z

219

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

SciTech Connect (OSTI)

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

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

2005-09-30T23:59:59.000Z

220

Readiness Assessment for MF-628 Drum Treatment Facility - Advanced...  

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

CONDUCT OF OPERATIONS (OP) Objective: OP.1 Adequate and correct procedures and safety limits are in place for operating the DTF ventilation system and conducting treatment...

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


221

Procedures for Students seeking accommodations.  

E-Print Network [OSTI]

This document outlines the procedures to be followed by students seeking accommodations in the following mathematics courses during Fall and Spring...

222

Procedure Advantages Disadvantages Saphenous Vein  

E-Print Network [OSTI]

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

Scott, Robert A.

223

Procedure Advantages Disadvantages Saphenous Vein  

E-Print Network [OSTI]

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

Scott, Robert A.

224

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

SciTech Connect (OSTI)

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

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

2013-07-08T23:59:59.000Z

225

Purchasing Policy and Procedures Page 1 Purchasing Policy and Procedures  

E-Print Network [OSTI]

Controller Responsible Offices: Purchasing Resource Services Controller's Office Origination Date: December 1Purchasing Policy and Procedures Page 1 4-1-2010 Purchasing Policy and Procedures Policy Statement are followed. Purchasing Resource Services (PRS), which is part of University Services, is the single point

Shahriar, Selim

226

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

SciTech Connect (OSTI)

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

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

2000-04-21T23:59:59.000Z

227

Residential Mail Procedures Residential Mail Services  

E-Print Network [OSTI]

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

Buehrer, R. Michael

228

LOCKOUT/TAGOUT Policy & Procedure  

E-Print Network [OSTI]

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

Berdichevsky, Victor

229

Fuel Station Procedure Applicability All  

E-Print Network [OSTI]

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

Moore, Paul A.

230

STANDARD OPERATING PROCEDURES Site Selection  

E-Print Network [OSTI]

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

Fischer, Emily V.

231

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

SciTech Connect (OSTI)

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

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

2013-09-19T23:59:59.000Z

232

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

SciTech Connect (OSTI)

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

Peters, T.; Fink, S.

2012-04-24T23:59:59.000Z

233

Specified assurance level sampling procedure  

SciTech Connect (OSTI)

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.

Willner, O.

1980-11-01T23:59:59.000Z

234

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

SciTech Connect (OSTI)

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

Michael L. Abbott; Keith A. Daum

2011-08-01T23:59:59.000Z

235

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

SciTech Connect (OSTI)

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

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

2013-04-26T23:59:59.000Z

236

Surface Environmental Surveillance Procedures Manual  

SciTech Connect (OSTI)

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.

Hanf, RW; Dirkes, RL

1990-02-01T23:59:59.000Z

237

Forrestal Security and Safety Procedures  

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

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.

1983-02-02T23:59:59.000Z

238

TRAITEMENT DES EFFLUENTS WASTE TREATMENT  

E-Print Network [OSTI]

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

Boyer, Edmond

239

Graduate School of Journalism Interim Grievance Procedures  

E-Print Network [OSTI]

Graduate School of Journalism Interim Grievance Procedures Introduction The following procedures the Dean to conduct a hearing under the formal grievance procedures described in this statement. Those procedures, like the procedures of other schools, provide for a final appeal to the University Provost

Qian, Ning

240

EECBG Program Notice 10-014  

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

use competitive proposal procedures for qualifications-based procurement of architecturalengineering professional services whereby competitors' qualifications are evaluated and...

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


241

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

SciTech Connect (OSTI)

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

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

2011-09-01T23:59:59.000Z

242

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

SciTech Connect (OSTI)

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

Peters, T.; Fink, S.

2011-06-22T23:59:59.000Z

243

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

SciTech Connect (OSTI)

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

Unknown

2002-02-08T23:59:59.000Z

244

SAFETY PROCEDURE SP-24 NATIONAL HIGH MAGNETIC  

E-Print Network [OSTI]

SAFETY PROCEDURE SP-24 NATIONAL HIGH MAGNETIC FIELD LABORATORY NHMFL FLORIDA STATE UNIVERSITY SAFETY PROCEDURE SP-24 VISITOR AND CONTRACTOR SAFETY DIRECTOR, ENVIRONMENTAL, HEALTH, SAFETY & SECURITY Angela Sutton

Weston, Ken

245

Export Authorizations - Procedures | Department of Energy  

Energy Savers [EERE]

Export Authorizations - Procedures Export Authorizations - Procedures Part II, Section 202(e) of the Federal Power Act (FPA) states that exports of electric energy should be...

246

West Virginia University 1 Policies and Procedures  

E-Print Network [OSTI]

West Virginia University 1 Policies and Procedures In this Section: · Academic Integrity a Charge of Academic Dishonesty · Appeal Procedures for Cases Involving Academic Dishonesty Academic

Mohaghegh, Shahab

247

Postdoctoral Hiring Procedures | Argonne National Laboratory  

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

Hiring Procedures The Postdoctoral Office at DEP coordinates and facilitates the application, review, and hiring procedures for all postdoctoral candidates, following the...

248

Statler College Scheduling Guidelines General Procedures  

E-Print Network [OSTI]

Statler College Scheduling Guidelines General Procedures Basic event information needed o Event Procedures Basic event information needed o Event name o Contact name, phone, email o expected number

Mohaghegh, Shahab

249

Presidential Permits - Procedures | Department of Energy  

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

Permits - 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...

250

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...

251

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)...

252

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

SciTech Connect (OSTI)

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

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

2010-01-27T23:59:59.000Z

253

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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 - SeptemberMicroneedles for4-16 FORPoints ofProbingDewetting

254

Developer Installed Treatment Plants  

E-Print Network [OSTI]

-installed treatment plants. These treatment plants are more commonly known as package wastewater treatment plants. 1

unknown authors

2008-01-01T23:59:59.000Z

255

EML Procedures Manual, HASL-300  

SciTech Connect (OSTI)

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.

Not Available

1981-09-28T23:59:59.000Z

256

Budget Reconciliation Procedures Reference Guide  

E-Print Network [OSTI]

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

Shull, Kenneth R.

257

Cooperative Education Detailed Operational Procedures  

E-Print Network [OSTI]

credits of Cooperative education for one of the required elective courses in the ME programME 3990 Cooperative Education Detailed Operational Procedures Overview Cooperative education and Aeronautical Engineering faculty. Cooperative education is not a required component of the ME program

de Doncker, Elise

258

EMISSIONS TO AIR OPERATIONAL PROCEDURE  

E-Print Network [OSTI]

EMISSIONS TO AIR OPERATIONAL PROCEDURE Swansea University Estates Services Singleton Park Swansea to Air Department: Estates and Facilities Site: All Author: Ambreen Jahangir Approved by: Mark Durdin PURPOSE: To minimise emissions and discharges to air from boilers, fume cupboards, air conditioning

Harman, Neal.A.

259

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

SciTech Connect (OSTI)

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

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

2013-08-08T23:59:59.000Z

260

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

SciTech Connect (OSTI)

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

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

1993-05-01T23:59:59.000Z

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


261

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

SciTech Connect (OSTI)

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

C. Wilson

2000-09-30T23:59:59.000Z

262

Test procedure for boxed waste assay system  

SciTech Connect (OSTI)

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.

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

1994-12-07T23:59:59.000Z

263

Policies, Procedures and Guidelines Complete Policy Title  

E-Print Network [OSTI]

Policies, Procedures and Guidelines Complete Policy Title: Procedures for Faculty Appeal Tribunals are used in these procedures: 1. `Appellant' means a faculty member who is entitled to appeal a tenure, within the Policy, Section IV, clauses 6(a) and 6(b). II Documents Governing Appeal Procedures

Hitchcock, Adam P.

264

Policies, Procedures and Guidelines Complete Policy Title  

E-Print Network [OSTI]

Policies, Procedures and Guidelines Complete Policy Title: Faculty General Grievance Procedure. OBJECTIVE This Procedure is designed to provide McMaster faculty members with prompt and impartial by existing, specific review procedures. It is intended to facilitate and promote informal resolution

Haykin, Simon

265

Policies, Procedures and Guidelines Complete Policy Title  

E-Print Network [OSTI]

Policies, Procedures and Guidelines Complete Policy Title: Procedures for University Reviews copy held by the policy owner, the written copy prevails. #12;Procedures for University Reviews of Academic Departments April 28, 2005 1 Procedures for University Reviews of Academic Departments1 I

Haykin, Simon

266

Division of Human Resources University Grievance Procedures  

E-Print Network [OSTI]

Division of Human Resources University Grievance Procedures Employee Relations/ USF System Grievance Procedure Questions: (813) 974-2970 Rev. 12/2012 This procedure applies to Administration, Staff in this procedure are expressed in calendar days. If a deadline falls on a Saturday, Sunday or holiday, an action

Meyers, Steven D.

267

CSP Policies & Procedures Process for Grade Appeals  

E-Print Network [OSTI]

CSP Policies & Procedures Process for Grade Appeals Grade Appeals ­ Generally speaking, once grades

Leistikow, Bruce N.

268

LABORATORY ANIMAL FACILITIES STANDARD OPERATING PROCEDURE  

E-Print Network [OSTI]

4.A.22 LABORATORY ANIMAL FACILITIES STANDARD OPERATING PROCEDURE FOR OPERATION/MAINTENANCE. 2.0 Scope This procedure applies to all personnel needing to operate this equipment. 3.0 Procedure 3 OF QUANTIFLEX ANESTHESIA MACHINE/ SURGIVET SAV2500 VENTILATOR UNIT 1.0 Purpose This procedure outlines how

Krovi, Venkat

269

Ris-R-1263(EN) Procedures for Determination of  

E-Print Network [OSTI]

Plutonium procedure for seaweed 9 Plutonium procedure for 1-2 g sediment or soil 10 Americium procedure

270

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

SciTech Connect (OSTI)

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

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

2008-11-10T23:59:59.000Z

271

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

SciTech Connect (OSTI)

Engineering robust adhesion of the junction-box (j-box) is a hurdle typically encountered by photovoltaic (PV) module manufacturers during product development. Furthermore, there are historical incidences of adverse effects (e.g., fires) caused when the j-box/adhesive/module system has failed in the field. The addition of a weight to the j-box during the 'damp heat' IEC qualification test is proposed to verify the basic robustness of the j-box adhesion system. The details of the proposed test are described, in addition to the preliminary results conducted using representative materials and components.

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

2012-02-01T23:59:59.000Z

272

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

SciTech Connect (OSTI)

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

Pham, Binh T; Einerson, Jeffrey J

2014-07-01T23:59:59.000Z

273

CBFWA Wildlife Habitat Evaluation Procedures (HEP)CBFWA Wildlife Habitat Evaluation Procedures (HEP) (2006(2006--006006--00)00)  

E-Print Network [OSTI]

CBFWA Wildlife Habitat Evaluation Procedures (HEP)CBFWA Wildlife Habitat Evaluation Procedures (HEP 101HEP 101 Habitat Evaluation Procedures (HEP) developed byHabitat Evaluation Procedures (HEP

274

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

SciTech Connect (OSTI)

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

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

2013-02-25T23:59:59.000Z

275

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

SciTech Connect (OSTI)

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

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

1996-04-01T23:59:59.000Z

276

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

SciTech Connect (OSTI)

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

None

1981-04-01T23:59:59.000Z

277

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

SciTech Connect (OSTI)

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.

Not Available

1981-01-01T23:59:59.000Z

278

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

SciTech Connect (OSTI)

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

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

2013-05-01T23:59:59.000Z

279

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

SciTech Connect (OSTI)

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)

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

2006-07-01T23:59:59.000Z

280

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...

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


281

Waste segregation procedures and benefits  

SciTech Connect (OSTI)

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.

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

1990-01-01T23:59:59.000Z

282

Procedure for Planning and Conducting  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas ConchasPassive Solar Home DesignPresentationsSRS RespondsLift Plan Procedure Stanford

283

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

SciTech Connect (OSTI)

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

Sun, K. X.

2011-05-31T23:59:59.000Z

284

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

E-Print Network [OSTI]

2014 : Qualification aux fonctions de matre de confrences (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 conomie-gestion (mention B), Universit de

Brest, Universit de

285

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

286

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

287

Risk Management Procedures Category: Strategic Management  

E-Print Network [OSTI]

/POLICY SUPPORTED Risk Management Policy Tertiary Education Quality Standards Agency Act 2011 (TEQSA Act 2011) 21 Risk Management Procedures Category: Strategic Management 1. LEGISLATION/ENTERPRISE AGREEMENT. PROCEDURAL DETAILS 2.1. Responsibilities Entity / Officer Responsibilities Planning and Management Committee

288

SAFETY PROCEDURE SP-19 Revision 02  

E-Print Network [OSTI]

SAFETY PROCEDURE SP-19 Page 1 Revision 02 August 6, 2007 NATIONAL HIGH MAGNETIC FIELD LABORATORY NHMFL FLORIDA STATE UNIVERSITY SAFETY PROCEDURE SP-19 MAGNETIC FIELD SAFETY DIRECTOR, ENVIRONMENTAL, HEALTH, SAFETY & SECURITY Angela Sutton

Weston, Ken

289

Segmentation and visualization for cardiac ablation procedures  

E-Print Network [OSTI]

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 ...

Depa, Michal

2011-01-01T23:59:59.000Z

290

POLICY: A:VPFA # / Purchasing Policy PROCEDURES  

E-Print Network [OSTI]

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

Martin, Jeff

291

Proposal Submittal and Scheduling Procedures for Macromolecular...  

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

Proposal Submittal and Scheduling Procedures for Macromolecular Crystallography Beam time for macromolecular crystallography projects is obtained by submitting an SSRL...

292

Delegation Procedures - DOE Directives, Delegations, and Requirements  

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

Energy's primary means of establishing policies, requirements, responsibilities, and procedures for Departmental elements and contractors. Directives Program Management Camille...

293

PROCEDURES and INSTRUCTIONS for SUBMITTING FINAL ...  

E-Print Network [OSTI]

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

saerens

2010-04-16T23:59:59.000Z

294

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

SciTech Connect (OSTI)

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

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

2012-05-11T23:59:59.000Z

295

Environmental Measurements Laboratory (EML) procedures manual  

SciTech Connect (OSTI)

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)

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

1990-11-01T23:59:59.000Z

296

Standards and Procedures for Promotion and Tenure  

E-Print Network [OSTI]

Appendix C Standards and Procedures for Promotion and Tenure I. Preamble This document sets forth standards and procedures for faculty promotions and appointments to tenure. These standards and procedures by university needs, plans, and resources. II. Standards The criteria outlined below are, of necessity

Heller, Barbara

297

Faculty Code Chapter 28 Adjudication Filing Procedures  

E-Print Network [OSTI]

Faculty Code Chapter 28 Adjudication Filing Procedures Secretary of the Faculty 10/2014 #12;Page 1 |Adjudication Introduction| Chapter 28 of the Faculty Code sets forth the adjudicative procedures to be used resolution procedures are available at any time during the resolution process, including the time period

Van Volkenburgh, Elizabeth

298

Dartmouth College Employment Policies and Procedures Manual  

E-Print Network [OSTI]

Dartmouth College Employment Policies and Procedures Manual Policy last updated: April 25, 2008 Grievance Procedure, Equal Opportunity Applies to: All employees Policy Statement: Dartmouth College of the Equal Opportunity Policy may bring a complaint under the Equal Opportunity Grievance Procedure. In some

Myers, Lawrence C.

299

PROCEDURES FOR THE SEARCH, APPOINTMENT, OR REAPPOINTMENT  

E-Print Network [OSTI]

1 PROCEDURES FOR THE SEARCH, APPOINTMENT, OR REAPPOINTMENT OF THE PRESIDENT AND VICE- CHANCELLOR of Senate establish procedures for the recommendation and selection of the President and shall subsequently appoint the President. The following procedures determine the method by which the Board of Governors

Victoria, University of

300

UNIVERSITY OF FLORIDA RULES AND PROCEDURES  

E-Print Network [OSTI]

UNIVERSITY OF FLORIDA RULES AND PROCEDURES OF THE STUDENT SENATE ____________________________________________________________ Issued by the Office of the Student Senate Special Committee on Rules and Procedures October 2008 Amended through February, 2014 #12;#12;RULES AND PROCEDURES OF THE STUDENT SENATE TABLE OF CONTENTS

Roy, Subrata

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


301

Competency Patient Care Sub Domain Procedures  

E-Print Network [OSTI]

Competency Patient Care Sub Domain Procedures Learning Objective Understands informed consent and performs uncomplicated procedures on patients or in simulation Milestones Year I Year II Year III Year IV Mid End Mid End Mid End Mid End · Defines elements of informed consent for procedures · Explains

Leistikow, Bruce N.

302

Automated Operating Procedures for Transfer Limits  

E-Print Network [OSTI]

Automated Operating Procedures for Transfer Limits Final Project Report Power Systems Engineering · Illinois · Iowa State · Texas A&M · Washington State · Wisconsin Automated Operating Procedures operating procedures to establish system constraints, particularly in regards to transfer limits across

303

UCSD Implementing Procedures 36/Classification of Positions  

E-Print Network [OSTI]

UCSD Implementing Procedures (HR-S-1) 36/Classification of Positions I. REFERENCES AND RELATED POLICIES A. UCSD Implementing Procedures 20 ­ Recruitment B. UC PPSM 36 - Classification of Positions C shall be obtained prior to any commitment to the concerned individual. III. PROCEDURES A. New

Tsien, Roger Y.

304

STANDARD OPERATING PROCEDURES Annual Site Maintenance  

E-Print Network [OSTI]

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

Fischer, Emily V.

305

PHYSICAL PLANT OPERATING POLICY AND PROCEDURE  

E-Print Network [OSTI]

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

Gelfond, Michael

306

The Effects of a Multicomponent Intervention on Treatment Integrity of Counterconditioning for Aggression in Dogs  

E-Print Network [OSTI]

The purpose of this study was to examine the effects of consumer management procedures on dog owner treatment integrity. A within subjects comparison was made. The primary dependent variable was treatment integrity. Errors ...

Savage, Kristyn Echterling

2011-12-31T23:59:59.000Z

307

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

E-Print Network [OSTI]

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...

Ghetti, Claire

2011-06-27T23:59:59.000Z

308

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

SciTech Connect (OSTI)

Modular HTGR designs were developed to provide natural safety, which prevents core damage under all design basis accidents and presently envisioned severe accidents. The principle that guides their design concepts is to passively maintain core temperatures below fission product release thresholds under all accident scenarios. This level of fuel performance and fission product retention reduces the radioactive source term by many orders of magnitude and allows potential elimination of the need for evacuation and sheltering beyond a small exclusion area. This level, however, is predicated on exceptionally high fuel fabrication quality and performance under normal operation and accident conditions. Germany produced and demonstrated high quality fuel for their pebble bed HTGRs in the 1980s, but no U.S. manufactured fuel had exhibited equivalent performance prior to the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. The design goal of the modular HTGRs is to allow elimination of an exclusion zone and an emergency planning zone outside the plant boundary fence, typically interpreted as being about 400 meters from the reactor. To achieve this, the reactor design concepts require a level of fuel integrity that is better than that claimed for all prior US manufactured TRISO fuel, by a few orders of magnitude. The improved performance level is about a factor of three better than qualified for German TRISO fuel in the 1980s. 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 1250C 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 1150C, 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 1250C, 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 1150C and the degree of margin available in the fuel system. This continues to be an active area of study internationally.

David Petti

2014-06-01T23:59:59.000Z

309

Radiological Work Planning and Procedures  

E-Print Network [OSTI]

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...

Kurtz, J E

2000-01-01T23:59:59.000Z

310

Writer`s guide for technical procedures  

SciTech Connect (OSTI)

A primary objective of operations conducted in the US Department of Energy (DOE) complex is safety. Procedures are a critical element of maintaining a safety envelope to ensure safe facility operation. This DOE Writer`s Guide for Technical Procedures addresses the content, format, and style of technical procedures that prescribe production, operation of equipment and facilities, and maintenance activities. The DOE Writer`s Guide for Management Control Procedures and DOE Writer`s Guide for Emergency and Alarm Response Procedures are being developed to assist writers in developing nontechnical procedures. DOE is providing this guide to assist writers across the DOE complex in producing accurate, complete, and usable procedures that promote safe and efficient operations that comply with DOE orders, including DOE Order 5480.19, Conduct of Operations for DOE Facilities, and 5480.6, Safety of Department of Energy-Owned Nuclear Reactors.

NONE

1998-12-01T23:59:59.000Z

311

HUMAN RELIABILITY ANALYSIS FOR COMPUTERIZED PROCEDURES  

SciTech Connect (OSTI)

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.

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

2011-09-01T23:59:59.000Z

312

Safe Operating Procedure SAFETY AUDIT GUIDELINES FOR BIOSAFETY LEVEL 2  

E-Print Network [OSTI]

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

Farritor, Shane

313

PROCEDURES FOR ACCESS TO AND CORRECTION OF INFORMATION Procedural Authority: University Secretary Effective Date: January, 2010  

E-Print Network [OSTI]

PROCEDURES FOR ACCESS TO AND CORRECTION OF INFORMATION Procedural Authority: University Secretary Effective Date: January, 2010 Procedural Officer: University Archivist Supersedes: New Last Editorial Change of these procedures is to set out how the university will manage: · freedom of information requests; · requests

Victoria, University of

314

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

SciTech Connect (OSTI)

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

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

2011-07-08T23:59:59.000Z

315

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

SciTech Connect (OSTI)

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

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

2013-03-18T23:59:59.000Z

316

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

SciTech Connect (OSTI)

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

Michael L. Abbott; Binh T. Pham

2012-06-01T23:59:59.000Z

317

National High Magnetic Field Laboratory - Policies and Procedures  

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

Lab Policies & Procedures Arrow Magnet Lab Policies and Procedures Numerous policies and procedures are in place at the Magnet Lab. Follow these links to learn more about them:...

318

Forecasting Dangerous Inmate Misconduct: An Applications of Ensemble Statistical Procedures  

E-Print Network [OSTI]

of Ensemble Statistical Procedures ? Richard A. Berk Brianpopular classi?cation procedures do no better than theand employ classi?cation procedures that identify inmates

Richard A. Berk; Brian Kriegler; Jong-Ho Baek

2011-01-01T23:59:59.000Z

319

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...

320

Texas A&M AgriLife Extension Service Procedures 21.99.99.X0.01 Inventory Procedures  

E-Print Network [OSTI]

Texas A&M AgriLife Extension Service Procedures 21.99.99.X0.01 Inventory Procedures Approved: JulyLife Extension Service Procedures 21.99.99.X0.01 Inventory Procedures Page 1 of 1 PROCEDURE STATEMENT Texas A in regulations. REASON FOR PROCEDURE This procedure outlines the process and responsibilities regarding

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


321

Radiological Work Planning and Procedure  

SciTech Connect (OSTI)

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.

KURTZ, J.E.

2000-01-01T23:59:59.000Z

322

A general design for energy test procedures  

SciTech Connect (OSTI)

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.

Meier, Alan

2000-06-15T23:59:59.000Z

323

Summative Mass Closure: Laboratory Analytical Procedure (LAP...  

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

Prepared under Task No. BB072230 NREL Laboratory Analytical Procedures for standard biomass analysis are available electronically at http:www.nrel.govbiomass...

324

Microsoft Word - EPRR_procedures_041015.docx  

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

Procedure for Routine Validation of Gamma Spectroscopy, Chemical Separation Alpha Spectrometry, Gas Proportional Counting, and Liquid Scintillation Analytical Data SOP-5169...

325

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...

326

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:...

327

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...

328

Postdoctoral Extension Procedures | Argonne National Laboratory  

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

Extension Procedures The Postdoctoral Office at DEP is responsible for processing the postdoctoral appointment extensions. It is important that all Argonne programmatic divisions...

329

Minnesota Environmental Coordination Procedures Act (Minnesota)  

Broader source: Energy.gov [DOE]

This Act is designed to streamline the review procedures for a given project that requires multiple environmental permits by establishing a mechanism in state government which will coordinate...

330

STANDARD OPERATING PROCEDURE ACIDS CONTAINING PHOSPHOROUS  

E-Print Network [OSTI]

12.1 STANDARD OPERATING PROCEDURE for ACIDS CONTAINING PHOSPHOROUS Location(s): ___________________________________________________ Chemical(s): Hypophosphorous acid, methylphosphonic acid, phosphonic acid, phosphoric acid, phosphorous

Pawlowski, Wojtek

331

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...

332

Hazardous Material Packaging for Transport - Administrative Procedures  

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

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

1986-09-30T23:59:59.000Z

333

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...

334

Hybrid LP/SDP Bounding Procedure  

E-Print Network [OSTI]

Hybrid LP/SDP Bounding Procedure. Fabio Furini1 and Emiliano Traversi2. 1 LIPN, Universit Paris 13, 93430 Villetaneuse, France.

2012-10-24T23:59:59.000Z

335

UCSD Implementing Procedures Effective Date: July 1, 1996 Page 1  

E-Print Network [OSTI]

UCSD Implementing Procedures (HR-S-1/Definitions of Terms B. UCSD Implementing Procedures 14/Affirmative Action C. UCSD Implementing Procedures 23/Performance Appraisal D. UC PPSM 30/Salary E. UCSD Implementing Procedures 30/Salary Equity Increase

Tsien, Roger Y.

336

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

SciTech Connect (OSTI)

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.

Not Available

1992-03-01T23:59:59.000Z

337

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...

338

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

SciTech Connect (OSTI)

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

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

1997-07-01T23:59:59.000Z

339

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

SciTech Connect (OSTI)

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

D. P. Blanchard; R. W. Youngblood

2014-06-01T23:59:59.000Z

340

UC Davis Policy and Procedure Manual Introduction  

E-Print Network [OSTI]

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

California at Davis, University of

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


341

Safe Operating Procedure (Reviewed 7/09)  

E-Print Network [OSTI]

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

Farritor, Shane

342

Safe Operating Procedure (Reviewed 7/09)  

E-Print Network [OSTI]

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

Farritor, Shane

343

Safe Operating Procedure (Reviewed 7/09)  

E-Print Network [OSTI]

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

Farritor, Shane

344

Safe Operating Procedure (Reviewed 7/09)  

E-Print Network [OSTI]

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

Farritor, Shane

345

Safe Operating Procedure (Revised 9/10)  

E-Print Network [OSTI]

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

Farritor, Shane

346

Safe Operating Procedure (Reviewed 7/09)  

E-Print Network [OSTI]

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

Farritor, Shane

347

Safe Operating Procedure (Reviewed 7/09)  

E-Print Network [OSTI]

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

Farritor, Shane

348

Safe Operating Procedure (Reviewed 7/09)  

E-Print Network [OSTI]

.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

Farritor, Shane

349

Safe Operating Procedure SAFETY PROTOCOL: Rb-86  

E-Print Network [OSTI]

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

Farritor, Shane

350

Safe Operating Procedure (Reviewed 7/09)  

E-Print Network [OSTI]

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

Farritor, Shane

351

Safe Operating Procedure (Reviewed 7/09)  

E-Print Network [OSTI]

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

Farritor, Shane

352

Spills of Radioactive Materials -Emergency Procedures  

E-Print Network [OSTI]

to radioactive waste container. For surface decontamination, use soap and water and cleansers appropriateSpills of Radioactive Materials - Emergency Procedures Procedure: 7.53 Created: 1/16/2014 Version for injured personnel. B. Applicability/scope This policy applies to all facilities where radioactive

Jia, Songtao

353

ADMINISTRATION AND FINANCE POLICIES AND PROCEDURES  

E-Print Network [OSTI]

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

Rusu, Adrian

354

Safe Operating Procedure (Created 5/11)  

E-Print Network [OSTI]

://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

Farritor, Shane

355

Academic Policies and Procedures Graduate Programs  

E-Print Network [OSTI]

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

Jiang, Huiqiang

356

PUBLIC INTEREST DISCLOSURE (PID) POLICY AND PROCEDURES  

E-Print Network [OSTI]

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

Greenslade, Diana

357

HEALTH AND SAFETY PROCEDURES -Major Projects  

E-Print Network [OSTI]

HEALTH AND SAFETY PROCEDURES - Major Projects HEALTH & SAFETY UNIT SPRING 2006 #12;CONTENTS of this document is to provide the University with a summary of the principle activities in construction projects the reliance on physical controls and use of personnel protective equipment. The procedures that consider

358

A diagnostic procedure for multivariate quality control  

E-Print Network [OSTI]

. 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...

Keserla, Adhinarayan A.

1993-01-01T23:59:59.000Z

359

9 TOWARD A MODEL OF ACQUIRING PROCEDURES  

E-Print Network [OSTI]

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

Kieras, David E.

360

Policy Procedure Administrative Directive Policy No.  

E-Print Network [OSTI]

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

Northern British Columbia, University of

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


361

Procedure Based Help Desk System Akira Takano  

E-Print Network [OSTI]

tools for help desk systems have become available [1]. When a help desk system is developed by usingProcedure Based Help Desk System Akira Takano Information Technology R&D Center Mitsubishi Electric kanae@isl.melco.co.jp ABSTRACT In this paper, we describe an outline of "Procedure based help desk

362

Colorado School of Mines Service Center Procedures  

E-Print Network [OSTI]

will usually develop and incorporate its own indirect cost rate in order to recover utilities, space School of Mines Service Center Procedures - 2 - I. PURPOSE CSM conducts research under Government sponsored awards. Therefore, service center procedures must reflect government regulatory costing principles

363

Procedures for Preparing the Research Project Proposal (Revised: March 5, 2010) 1 PROCEDURES FOR A PROJECT  

E-Print Network [OSTI]

FOR A PROJECT: for the Master of Science in Human-Computer InteractionProcedures for Preparing the Research Project Proposal (Revised: March 5, 2010) 1 PROCEDURES the Research Project Proposal (Revised: March 5, 2010) 2 Contents HCI GRADUATE FACULTY

Zhou, Yaoqi

364

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

SciTech Connect (OSTI)

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.

Dalton, W.J.

1997-06-30T23:59:59.000Z

365

\\\\files.umn.edu\\DRS\\Shared\\Departmental Information\\Policies and Procedures Policies and Procedures  

E-Print Network [OSTI]

1 \\\\files.umn.edu\\DRS\\Shared\\Departmental Information\\Policies and Procedures Policies and Procedures Manual 2013-2014 (Updated 10/13) #12;2 Table of Contents General Policies 4 - 5 Appropriate User Groups Locker Rooms Climbing Wall 28 Court Sports 29-30 Participation Reservation Procedures #12

Amin, S. Massoud

366

Appendix A: Committee on Student Conduct Hearing Procedures Committee on Student Conduct Hearing Procedures  

E-Print Network [OSTI]

Appendix A: Committee on Student Conduct Hearing Procedures Committee on Student Conduct Hearing Procedures A. Introduction B. Parties to the Complaint C. Committee and Panels D. Cases of Physical. For the purpose of these procedures, the parties are identified as the University presenter and the accused

Amin, S. Massoud

367

Policies, Procedures and Guidelines Duplicate and Replacement Parchments Diplomas and Certificates Procedures1.doc.doc  

E-Print Network [OSTI]

Policies, Procedures and Guidelines Duplicate and Replacement Parchments Diplomas and Certificates Procedures1.doc.doc Complete Policy Title: Duplicate and Replacement Parchments, Diplomas and Certificates Procedures Policy Number (if applicable): Approved by: Senate Date of Most Recent Approval: March 14, 2007

Haykin, Simon

368

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

E-Print Network [OSTI]

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

Kirschner, Denise

369

Texas A&M AgriLife Research Procedures 29.01.03.A0.01 Information Resource Procedures  

E-Print Network [OSTI]

Texas A&M AgriLife Research Procedures 29.01.03.A0.01 Information Resource Procedures Approved, 2011 August 24, 2012 Next Scheduled Review: August 24, 2014 Texas A&M AgriLife Research Procedures 29.01.03.A0.01 Information Resource Procedures Page 1 of 19 PROCEDURE STATEMENT This procedure establishes

370

Study of two sampling procedures for the valorization of metal hydroxide sludge as pollutant trapper  

E-Print Network [OSTI]

treatment, CrVI 1 Introduction Industrial aqueous pollution (heavy metals) accounts for 30 to 40% of all1 Study of two sampling procedures for the valorization of metal hydroxide sludge as pollutant@emse.fr Abstract: For the valorisation of metal hydroxide sludge as adsorbent of pollutant, it is necessary to make

Boyer, Edmond

371

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

SciTech Connect (OSTI)

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.

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

1996-12-31T23:59:59.000Z

372

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

SciTech Connect (OSTI)

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

Binh T. Pham

2014-02-01T23:59:59.000Z

373

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]

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

Liley, David

374

Onsite Wastewater Treatment Systems: Aerobic Treatment Unit  

E-Print Network [OSTI]

wastewater treatment systems use. They remove 85 to 98 percent of the organic matter and solids from the wastewater, producing effluent as clean as that from munici- pal wastewater treatment plants, and cleaner than that from conventional septic tanks.... Onsite wastewater treatment systems Single-compartment trash tank Chlorinator Aerobic treatment unit Spray heads Pump tank Bruce Lesikar Professor and Extension Agricultural Engineer The Texas A&M System Aerobic treatment units, which are certified...

Lesikar, Bruce J.

2008-10-31T23:59:59.000Z

375

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

SciTech Connect (OSTI)

The United States Department of Energys 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 Energys lead laboratory for nuclear energy development. The ATR is one of the worlds premiere test reactors for performing long term, high flux, and/or large volume irradiation test programs. These AGR fuel experiments will be irradiated over the next ten years to demonstrate and qualify new particle fuel for use in high temperature gas reactors. The experiments, which will each consist of six separate capsules, will be irradiated in an inert sweep gas atmosphere with individual on-line temperature monitoring and control for each capsule. The swept gas will also have on-line fission product monitoring to track performance of the fuel in each individual capsule during irradiation.

S. Blaine Grover; David A. Petti

2007-09-01T23:59:59.000Z

376

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

SciTech Connect (OSTI)

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

Molvik, A W; Simonen, T C

2009-07-17T23:59:59.000Z

377

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

SciTech Connect (OSTI)

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

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

1993-10-01T23:59:59.000Z

378

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

SciTech Connect (OSTI)

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

CANNELL, G.R.

2006-09-11T23:59:59.000Z

379

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

SciTech Connect (OSTI)

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

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

1996-04-01T23:59:59.000Z

380

Computational procedures for weighted projective spaces  

E-Print Network [OSTI]

This is a pdf print of the homonymous Maple file, freely available at http://www.maplesoft.com/applications/view.aspx?SID=127621, providing procedures which are able to produce the toric data associated with a (polarized) weighted projective space i.e. fans, polytopes and their equivalences. More originally it provides procedures which are able to detect a weights vector Q starting from either a fan or a polytope: we will call this process the recognition of a (polarized) weighted projective space. Moreover it gives procedures connecting polytopes of a polarized weighted projective space with an associated fan and viceversa.

Rossi, Michele

2011-01-01T23:59:59.000Z

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


381

Health Code Number (HCN) Development Procedure  

SciTech Connect (OSTI)

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.

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

2013-09-01T23:59:59.000Z

382

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

SciTech Connect (OSTI)

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

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

2013-05-31T23:59:59.000Z

383

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

SciTech Connect (OSTI)

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.

Ted Quinn; Jerry Mauck

2012-09-01T23:59:59.000Z

384

General Construction Company Private Development Procedure  

E-Print Network [OSTI]

administration and subcontractor management in the execution of each project. Generals current operations are very conducive to private development. However, the company can no longer rely on an oral system to relay historical processes and procedures...

Eason, Scott W.

2006-05-19T23:59:59.000Z

385

Financial Policy and Procedures for Reimbursable Work  

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

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.

1988-08-15T23:59:59.000Z

386

Safe Operating Procedure (Revised 11/11)  

E-Print Network [OSTI]

Generators Definition and Visual Determination of Opacity With regards to stack emissions, opacitySafe Operating Procedure (Revised 11/11) OPACITY OF EMISSIONS FROM COMBUSTION SOURCES (opacity) from combustion sources. Opacity monitoring & measurements are taken in accordance

Farritor, Shane

387

Athletic Training Admissions Procedures Truman State University  

E-Print Network [OSTI]

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

Gering, Jon C.

388

MAES Project Review Procedures SEMINAR FORMAT  

E-Print Network [OSTI]

MAES Project Review Procedures SEMINAR FORMAT The peer review seminar will be styled after oral the project's past accomplishments (if renewal) Discuss the new project proposal 2. Open Discussion ­ (approx

Maxwell, Bruce D.

389

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

390

VEHICLE OPERATING PROCEDURES DEPARTMENT OF BIOLOGICAL SCIENCE  

E-Print Network [OSTI]

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

Ronquist, Fredrik

391

Practical Procedures for Auditing Industrial Boiler Plants  

E-Print Network [OSTI]

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...

O'Neil, J. P.

1980-01-01T23:59:59.000Z

392

Policies, Procedures and Guidelines Complete Policy Title  

E-Print Network [OSTI]

processes to promote development and operation of sustainable buildings. #12;Policies, Procedures and Guidelines Complete Policy Title: Sustainable Building Policy Policy this electronic policy and the written copy held by the policy owner, the written copy prevails. Sustainable

Haykin, Simon

393

RECYCLING AND GENERAL WASTE MANAGEMENT OPERATIONAL PROCEDURE  

E-Print Network [OSTI]

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

Harman, Neal.A.

394

Procedures for sampling radium-contaminated soils  

SciTech Connect (OSTI)

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.

Fleischhauer, H.L.

1985-10-01T23:59:59.000Z

395

Policy and Procedures 1 HUMAN DEVELOPMENT AND FAMILY STUDIES  

E-Print Network [OSTI]

Policy and Procedures 1 HUMAN DEVELOPMENT AND FAMILY STUDIES POLICY AND PROCEDURES MANUAL Approved by HDFS Faculty October, 2011 #12;Policy and Procedures 2 Contents Page I. Department Mission. Standing and Ad Hoc Committees 6-9 III. Department Procedures 9 A. General Operating Procedures

Rock, Chris

396

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

SciTech Connect (OSTI)

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

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

2010-10-01T23:59:59.000Z

397

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

SciTech Connect (OSTI)

The United States Department of Energys 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 Energys lead laboratory for nuclear energy development. These AGR fuel experiments will be irradiated over the next ten years to demonstrate and qualify new particle fuel for use in high temperature gas reactors. The experiments, which will each consist of six separate capsules, will be irradiated in an inert sweep gas atmosphere with individual on-line temperature monitoring and control for each capsule. The swept gas will also have on-line fission product monitoring to track performance of the fuel in each individual capsule during irradiation. The design of the first experiment (designated AGR-1) was completed in 2005, and the fabrication and assembly of the test train as well as the support systems and fission product monitoring system that monitor and control the experiment during irradiation were completed in September 2006. The experiment was inserted in the ATR in December 2006, and is serving as a shakedown test of the multi-capsule experiment design that will be used in the subsequent irradiations as well as a test of the early variants of the fuel produced under this program. The experiment test train as well as the monitoring, control, and data collection systems are discussed and the status of the experiment is provided.

S. Blaine Grover; David A. Petti

2008-10-01T23:59:59.000Z

398

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

SciTech Connect (OSTI)

The United States Department of Energys 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 Energys lead laboratory for nuclear energy development. The ATR is one of the worlds premiere test reactors for performing long term, high flux, and/or large volume irradiation test programs. These AGR fuel experiments will be irradiated over the next ten years to demonstrate and qualify new particle fuel for use in high temperature gas reactors. The goals of the irradiation experiments are to provide irradiation performance data to support fuel process development, to qualify fuel for normal operating conditions, to support development and validation of fuel performance and fission product transport models and codes, and to provide irradiated fuel and materials for post irradiation examination (PIE) and safety testing. The experiments, which will each consist of six separate capsules, will be irradiated in an inert sweep gas atmosphere with individual on-line temperature monitoring and control for each capsule. The swept gas will also have on-line fission product monitoring to track performance of the fuel in each individual capsule during irradiation.

S. Blaine Grover

2006-10-01T23:59:59.000Z

399

Ensemble Procedures for Finding High Risk Prison Inmates  

E-Print Network [OSTI]

We make no claims that the procedures we have applied are insense optimal. However, procedures like those we used wouldEnsemble Procedures for Finding High Risk Prison Inmates ?

Richard A. Berk; Jong-Ho Baek

2011-01-01T23:59:59.000Z

400

Guidelines and Procedures for Responding to Allegations of  

E-Print Network [OSTI]

Guidelines and Procedures for Responding to Allegations of Research Misconduct1 February 11, 2009 1 Formerly, Operating Rules and Procedures of the Standing Committee on Research Misconduct 1 #12;Table. Voting Procedures

Stowell, Michael

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


401

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

Energy Savers [EERE]

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

402

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...

403

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

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

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

404

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

Office of Environmental Management (EM)

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

405

Meeting Concerning Potential Test Procedures and Energy Conservation...  

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

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

406

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

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

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

407

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...

408

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

Office of Environmental Management (EM)

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

409

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...

410

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

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

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

411

Policy and Procedures for the Review of Federal Actions Impacting...  

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

Policy and Procedures for the Review of Federal Actions Impacting the Environment Policy and Procedures for the Review of Federal Actions Impacting the Environment This manual...

412

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

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

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...

413

Unified Procedures Applicable to Major Federal Actions Relating...  

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

Unified Procedures Applicable to Major Federal Actions Relating to Nuclear Activities Subject to Executive Order 12114 (State Department, 44 Fed Reg 65560) Unified Procedures...

414

CLOSEOUT PROCEDURES FOR RECOVERY ACT GRANTS UNDER THE WEATHERIZATION...  

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

CLOSEOUT PROCEDURES FOR RECOVERY ACT GRANTS UNDER THE WEATHERIZATION ASSISTANCE PROGRAM CLOSEOUT PROCEDURES FOR RECOVERY ACT GRANTS UNDER THE WEATHERIZATION ASSISTANCE PROGRAM This...

415

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...

416

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)...

417

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...

418

Forrestal Garage Parking Procedures, Revised August 12, 2010  

Broader source: Energy.gov [DOE]

Forrestal Garage Parking Procedures - The Forrestal Facility Parking Guide was created to define policies and procedures governing the assignment, use, and management of parking spaces controlled...

419

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...

420

Coordinate Measuring Machine Pit Artifact Inspection Procedure  

SciTech Connect (OSTI)

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.

Montano, Joshua D. [Los Alamos National Laboratory

2012-07-31T23:59:59.000Z

Note: This page contains sample records for the topic "treatment procedure qualification" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
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421

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

SciTech Connect (OSTI)

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.

Laurens, L. M. L.

2013-12-01T23:59:59.000Z

422

Texas A&M AgriLife Research Procedures 21.99.99.A0.01 Inventory Procedures  

E-Print Network [OSTI]

Texas A&M AgriLife Research Procedures 21.99.99.A0.01 Inventory Procedures Approved: July 15, 1998Life Research Procedures 21.99.99.A0.01 Inventory Procedures Page 1 of 1 PROCEDURE STATEMENT Texas A&M Agri and regulations, as well as Texas A&M University System (System) policies in regulations. REASON FOR PROCEDURE

423

Post-Treatment Hemodynamics of a Basilar Aneurysm and Bifurcation  

SciTech Connect (OSTI)

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.

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

2008-01-16T23:59:59.000Z

424

The Waste Management Quality Assurance Implementing Management Plan (QAIMP)  

E-Print Network [OSTI]

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

Albert editor, R.

2009-01-01T23:59:59.000Z

425

Standard Operating Procedure (SOP) -Milling Machine  

E-Print Network [OSTI]

Standard Operating Procedure (SOP) - Milling Machine · Keep all guards in place while operating the machine. · While operating the milling machine allow no one else to touch it. · Keep hands away from moving cutting tools. · Do not make measurements of the stock while the milling machine is powered. · Do

Veiga, Pedro Manuel Barbosa

426

Toolbox Safety Talk Hot Work Safety Procedures  

E-Print Network [OSTI]

Toolbox Safety Talk Hot Work Safety Procedures Environmental Health & Safety Facilities Safety-in sheet to Environmental Health & Safety for recordkeeping. "Hot Work" is defined as any temporary WORK Obtain a hot work permit from your supervisor or safety rep. Ensure fire/smoke detection

Pawlowski, Wojtek

427

GRADUATE PROGRAMS IN Guidelines and Procedures  

E-Print Network [OSTI]

student-faculty interaction. The city of Davis has been called the most "energy-conscious" city Sciences in the College of Letters and Science at UC Davis. The department has sixteen full-time senate1 GRADUATE PROGRAMS IN STATISTICS Guidelines and Procedures UNIVERSITY OF CALIFORNIA, DAVIS Fall

Nguyen, Danh

428

Safe Operating Procedure (Revised 10/11)  

E-Print Network [OSTI]

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

Farritor, Shane

429

Safe Operating Procedure (Reviewed 7/09)  

E-Print Network [OSTI]

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

Farritor, Shane

430

Safe Operating Procedure (Reviewed 7/09)  

E-Print Network [OSTI]

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

Farritor, Shane

431

Safe Operating Procedure (Reviewed 7/09)  

E-Print Network [OSTI]

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

Farritor, Shane

432

Revised November 2012 GRADE SUBMISSION PROCEDURES  

E-Print Network [OSTI]

are required to submit grades via MyUH or LAULIMA for all students by 4pm on the Tuesday following the finalUH. Therefore, for grades entered via LAULIMA, faculty will need to load grade via LAULIMA and then access My to the Grading Deadlines/Procedure Grades for students enrolled in the following courses will be processed

433

1983 EML Procedures Manual. 26th Edition  

SciTech Connect (OSTI)

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)

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

1983-01-01T23:59:59.000Z

434

FRENCH APPROVAL PROCEDURES FOR PYROTECHNICAL AUTOMOTIVE SAFETY  

E-Print Network [OSTI]

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

Paris-Sud XI, Université de

435

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

436

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

437

Policies, Procedures and Guidelines Complete Policy Title  

E-Print Network [OSTI]

Policies, Procedures and Guidelines Complete Policy Title: McMaster University Sustainability a high degree of vegetative surface while limiting the use of pesticides, harmful chemicals and the need; and · experiment with alternative paving methods that will incorporate vegetation. Transportation The University

Haykin, Simon

438

Environmental Health & Safety Policy & Procedure #24  

E-Print Network [OSTI]

Effects OBJECTIVE AND PURPOSE: The goal of this policy is to provide guidelines and procedures for the use Standard 1123. Fireworks are for outdoor use. Pyrotechnics Any device containing a chemical mixture displays will be approved. The individual or company responsible for transportation of display materials

Fernandez, Eduardo

439

Student Disability Transportation Policies and Procedures  

E-Print Network [OSTI]

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

Portman, Douglas

440

Experimental Procedures 2.1 Introduction  

E-Print Network [OSTI]

procedures utilised to characterise austempered ductile irons obtained in the present thesis. The experiments the experimental programme for austempered samples. before quenching in water with breaking silica tubes, manufactured by Fuji Electronic Industrial Co. Ltd., is a laboratory machine capable of implementing speci ed

Cambridge, University of

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


441

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

442

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

443

Chemical Hygiene Policy Procedure: 6.05  

E-Print Network [OSTI]

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 Chemicals in Laboratories, also referred to as the Laboratory Standard. This policy provides current general

Jia, Songtao

444

Chemical Spill Response Procedure Initial Response  

E-Print Network [OSTI]

Chemical Spill Response Procedure Initial Response 1. Advise lab occupants of the spill such as quantity spilled and chemical name. Risk Assessment 3. Conduct an initial risk assessment to determine if to the chemical spill. This link can be found at the bottom of the Campus Security homepage, http

445

BU BRAIN Self Service GRADING PROCEDURES  

E-Print Network [OSTI]

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

Suzuki, Masatsugu

446

PHYSICAL PLANT OPERATING POLICY AND PROCEDURE  

E-Print Network [OSTI]

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

Gelfond, Michael

447

Department of Geosciences Purchasing Card Policies & Procedures  

E-Print Network [OSTI]

, a department purchasing card is available in the Department of Geosciences Business Office. PCard Monthly the Business Office (i.e.: copying the PCard information for making future purchases) will result in immediate1 Department of Geosciences Purchasing Card Policies & Procedures The University of Arizona

Holliday, Vance T.

448

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

449

Combining Decision Procedures for Sorted Theories  

E-Print Network [OSTI]

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

Tinelli, Cesare

450

CONTROL VALVE TESTING PROCEDURES AND EQUATIONS  

E-Print Network [OSTI]

a coefficient that is independent of valve size and constant for geometrically similar valves. However in the publication "Control Valve Flow Coefficients" by Rahmeyer and Driskell and published in the Pipeline Journal of ASCE. Testing Procedures The flow coefficient is experimentally determined for different valve openings

Rahmeyer, William J.

451

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

452

Detailed Financial Procedures Page 1 of 3  

E-Print Network [OSTI]

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

Levi, Ran

453

LASER SAFETY MANUAL POLICIES AND PROCEDURES  

E-Print Network [OSTI]

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

Zhang, Yuanlin

454

ANNUAL INVENTORY PROCEDURES INVENTORY WORKSHEET RETURN  

E-Print Network [OSTI]

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

Provancher, William

455

Internship FBI Fingerprint Procedures and Additional Screenings  

E-Print Network [OSTI]

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

Gering, Jon C.

456

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

457

The Psychology Clinic Manual of Procedures and  

E-Print Network [OSTI]

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

Zhang, Yuanlin

458

UNIVERSITY OF NORTHERN BRITISH COLUMBIA Policies & Procedures  

E-Print Network [OSTI]

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

Bolch, Tobias

459

UNIVERSITY OF NORTHERN BRITISH COLUMBIA Policies & Procedures  

E-Print Network [OSTI]

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

Bolch, Tobias

460

Animal Care and Biosafety STANDARD OPERATING PROCEDURES  

E-Print Network [OSTI]

Banding The present SOP has been developed for mist netting and ground trapping procedure for most small solution 4. Alcohol based hand sanitizer 5. Pliers 6. Weighing dish 7. Bands (sufficient variety in numbers and sizes to accommodate all bird species that will be encountered) 8. Pesola scale 9. Cloth

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


461

Recommended Procedures for Measuring Radon Fluxes from  

E-Print Network [OSTI]

of Waste Management Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission#12;#12;Recommended Procedures for Measuring Radon Fluxes from Disposal Sites of Residual'nat the average annual l'elease of radon-222 from the disposal sites to t.he atmosp~1er0 by residuai radioactive

462

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

463

STANDARD OPERATING PROCEDURE DIMETHYL SULFOXIDE (DMSO)  

E-Print Network [OSTI]

be handled as hazardous waste. 8. Decontamination: Specific instructions: Wash items/surfaces with light12.1 STANDARD OPERATING PROCEDURE for DIMETHYL SULFOXIDE (DMSO) Location(s): ___________________________________________________ Chemical(s): Dimethyl Sulfoxide (DMSO) Specific Hazards: Combustible liquid, transport across skin barrier

Pawlowski, Wojtek

464

STANDARD OPERATING PROCEDURE Location(s): ___________________________________________________  

E-Print Network [OSTI]

of as hazardous waste. 8. Decontamination: Specific instructions: For light contamination of small areas or items12.1 STANDARD OPERATING PROCEDURE for PHENOL Location(s): ___________________________________________________ Chemical(s): Phenol Specific Hazards: May be fatal if inhaled. Harmful if absorbed through skin. Harmful

Pawlowski, Wojtek

465

MODIFIED KREIN FORMULA AND ANALYTIC PERTURBATION PROCEDURE  

E-Print Network [OSTI]

mathematical problem concerning perturbation of embedded eigen- values. For practical needs consisting of a single compact quantum well and few semi-infinite wires attached to it. In the theoretical-body scattering problem. In this paper we suggest a semi-analytic perturbation procedure which permits

466

Development of decontamination procedures for beef trimmings  

E-Print Network [OSTI]

beef by 1.3 log??CFU/g and had significantly lower APCs on days 7, 14, and 21 compared to the control and other treatments. These treatments, especially the LA+HW would be an acceptable intervention step to be further examined to assist...

Ebeling, Christine Suzanne

2012-06-07T23:59:59.000Z

467

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

SciTech Connect (OSTI)

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

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

2012-07-01T23:59:59.000Z

468

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

SciTech Connect (OSTI)

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

Pardini, A.F.

1995-10-01T23:59:59.000Z

469

GUIDELINES FOR STUDENTS AND STAFF ON STUDENT DISCIPLINE PROCEDURES  

E-Print Network [OSTI]

GUIDELINES FOR STUDENTS AND STAFF ON STUDENT DISCIPLINE PROCEDURES Contents 1. Introduction 2. Definition of Disciplinary Offences 3. Preliminary Procedures for Considering Disciplinary Offences 4. Procedures for the Consideration of Minor Offences 5. Procedures for the Consideration of Category B Offences

Greenaway, Alan

470

DACE procedures for dealing with complaints 1. Introduction  

E-Print Network [OSTI]

DACE procedures for dealing with complaints 1. Introduction We are required to be clear to all is the informal procedure). If any issue is not resolved by this means, the University procedure can be used by the complainant (ie the formal procedure). 2. Information to students and tutors Information should be made

Guo, Zaoyang

471

PROCEDURES FOR THE APPOINTMENT AND RE-APPOINTMENT  

E-Print Network [OSTI]

Page 1 PROCEDURES FOR THE APPOINTMENT AND RE-APPOINTMENT OF RESEARCH CENTRE DIRECTORS University: Mandated review: January, 2017 PURPOSE 1.00 The purpose of these procedures is to provide direction at the University of Victoria. PROCEDURES 2.00 The processes provided in these procedures are intended

Victoria, University of

472

Using Model-based Assurance to Strengthen Diagnostic Procedures  

E-Print Network [OSTI]

Using Model-based Assurance to Strengthen Diagnostic Procedures Robyn Lutz Jet Propulsion Lab diagnostic trees generated from system models are used to help check out diagnostic procedures. Diagnostic procedures are instructions used to isolate failures during operations. Assuring such procedures manually

Lutz, Robyn R.

473

NSF ITR Project General Notes on Trypsin Test Procedure  

E-Print Network [OSTI]

NSF ITR Project Fall 2004 General Notes on Trypsin Test Procedure: Automated performance procedure the assay still work"?) Calculation of the Z' ­ Factor (quality criteria) Manual performance procedure: (Uses/purpose of procedure: Setup a new assay. Use as basis for comparison with automated version

Kaber, David B.

474

Policy and Procedure Writing Tips University Policy Website  

E-Print Network [OSTI]

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

Pedersen, Tom

475

STANDARD OPERATING PROCEDURES Sampler Maintenance by Site Operators  

E-Print Network [OSTI]

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

Fischer, Emily V.

476

25.07.03.M1.01 Vendor Protest Procedures Page 1 of 2 STANDARD ADMINISTRATIVE PROCEDURE  

E-Print Network [OSTI]

25.07.03.M1.01 Vendor Protest Procedures Page 1 of 2 STANDARD ADMINISTRATIVE PROCEDURE 25.07.03.M1.01 Vendor Protest Procedures Approved July 18, 1997 Revised January 7, 2002 Revised May 22, 2007 Revised This Standard Administrative Procedure (SAP) details the steps necessary for a vendor to challenge a purchase

477

12.02 Institutional Procedures for Implementing Tenure Page 1 of 3 12.02 Institutional Procedures for Implementing Tenure  

E-Print Network [OSTI]

12.02 Institutional Procedures for Implementing Tenure Page 1 of 3 12.02 Institutional Procedures procedures for implementing tenure in accordance with this policy. Reason for Policy This policy provides guidance to system academic institutions in the development of tenure procedures, and the policy also

478

51.04.01.G0.01 Construction Project Procedure Page 1 of 2 STANDARD ADMINISTRATIVE PROCEDURE  

E-Print Network [OSTI]

51.04.01.G0.01 Construction Project Procedure Page 1 of 2 STANDARD ADMINISTRATIVE PROCEDURE 51.04.01.G0.01 Construction Project Procedure Approved September 14, 2000 Revised January 21, 2011 Next ___________________________________________________________________________________ This delegation of authority and procedure pertains to construction projects only and supersedes all existing

479

Procedure to Measure Indoor Lighting Energy Performance  

SciTech Connect (OSTI)

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.

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

2005-10-01T23:59:59.000Z

480

Nondestructive assay (NDA) techniques and procedures  

SciTech Connect (OSTI)

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.

Not Available

1994-05-01T23:59:59.000Z

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


481

Characterization of aerosols produced by surgical procedures  

SciTech Connect (OSTI)

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.

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

482

Roof Coating Procedures and Their Productivity Gains  

E-Print Network [OSTI]

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...

Bonaby, J.; Schaub, D.

2006-01-01T23:59:59.000Z

483

ITOUGH2 Software Qualification  

E-Print Network [OSTI]

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

Fraser, P.

2010-01-01T23:59:59.000Z

484

ITOUGH2 Software Qualification  

E-Print Network [OSTI]

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

Fraser, P.

2010-01-01T23:59:59.000Z

485

Chemical Processing Qualification Standard  

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

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

486

Mechanical Systems Qualification Standard  

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

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

487

Qualification of Alternative Fuels  

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

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

488

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 utilitys investment in generation or transmission before constructing a facility or entering into a...

489

Measurement and Treatment of Nuisance Odors at Wastewater Treatment Plants  

E-Print Network [OSTI]

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

Abraham, Samantha Margaret

2014-01-01T23:59:59.000Z

490

A procedure for oscillatory parameter identification  

SciTech Connect (OSTI)

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.

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

491

Index of /research/alcator/facility/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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-SeriesFlickrinformation for planningto FuelIndependentProcedures [ICO] Name Last

492

Property:FieldProcedures | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 No revisionEnvReviewNonInvasiveExploration Jump to:FieldProcedures Jump to: navigation, search Property Name

493

Sandia National Laboratories: Small Generator Interconnection 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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -theErikGroundbreaking WorkTransformationSiting Siting At theprogramProcedure

494

DOE Publishes Final Rule for Residential Furnace Fan Test Procedure...  

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

Residential Furnace Fan Test Procedure DOE Publishes Final Rule for Residential Furnace Fan Test Procedure January 3, 2014 - 12:00am Addthis The Department of Energy (DOE) has...

495

CRAD, System Operating Test Procedures - October 23, 2014 (EA...  

Office of Environmental Management (EM)

System Operating Test Procedures - October 23, 2014 (EA CRAD 31-05, Rev. 0) CRAD, System Operating Test Procedures - October 23, 2014 (EA CRAD 31-05, Rev. 0) October 23, 2014...

496

DEPARTMENT OF AGRICULTURAL ECONOMICS Faculty Tenure and Promotion Evaluation Procedures  

E-Print Network [OSTI]

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

Behmer, Spencer T.

497

Solar Energy to Benefit from New FERC Interconnection Procedures...  

Energy Savers [EERE]

Solar Energy to Benefit from New FERC Interconnection Procedures Solar Energy to Benefit from New FERC Interconnection Procedures October 30, 2014 - 5:15pm Addthis As a major win...

498

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...

499

On the Translation of Procedures to Finite Machines  

E-Print Network [OSTI]

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

Müller-Olm, Markus

500

On the Translation of Procedures to Finite Machines  

E-Print Network [OSTI]

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

Müller-Olm, Markus