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Note: This page contains sample records for the topic "integrated test plan" 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

System integration test plan for HANDI 2000 business management system  

SciTech Connect (OSTI)

This document presents the system integration test plan for the Commercial-Off-The-Shelf, PassPort and PeopleSoft software, and custom software created to work with the COTS products. The PP software is an integrated application for AP, Contract Management, Inventory Management, Purchasing and Material Safety Data Sheet. The PS software is an integrated application for Project Costing, General Ledger, Human Resources/Training, Payroll, and Base Benefits.

Wilson, D.

1998-08-24T23:59:59.000Z

2

Integrated development and testing plan for the plutonium immobilization project  

SciTech Connect (OSTI)

This integrated plan for the DOE Office of Fissile Materials Disposition (MD) describes the technology development and major project activities necessary to support the deployment of the immobilization approach for disposition of surplus weapons-usable plutonium. The plan describes details of the development and testing (D&T) tasks needed to provide technical data for design and operation of a plutonium immobilization plant based on the ceramic can-in-canister technology (''Immobilization Fissile Material Disposition Program Final Immobilization Form Assessment and Recommendation'', UCRL-ID-128705, October 3, 1997). The plan also presents tasks for characterization and performance testing of the immobilization form to support a repository licensing application and to develop the basis for repository acceptance of the plutonium form. Essential elements of the plant project (design, construction, facility activation, etc.) are described, but not developed in detail, to indicate how the D&T results tie into the overall plant project. Given the importance of repository acceptance, specific activities to be conducted by the Office of Civilian Radioactive Waste Management (RW) to incorporate the plutonium form in the repository licensing application are provided in this document, together with a summary of how immobilization D&T activities provide input to the license activity. The ultimate goal of the Immobilization Project is to develop, construct, and operate facilities that will immobilize from about 18 to 50 tonnes (MT) of U.S. surplus weapons usable plutonium materials in a manner that meets the ''spent fuel'' standard (Fissile Materials Storage and Disposition Programmatic Environmental Impact Statement Record of Decision, ''Storage and Disposition Final PEIS'', issued January 14, 1997, 62 Federal Register 3014) and is acceptable for disposal in a geologic repository. In the can-in-canister technology, this is accomplished by encapsulating the plutonium-containing ceramic forms within large canisters of high level waste (HLW) glass. Deployment of the immobilization capability should occur by 2006 and be completed within 10 years.

Kan, T.

1998-07-01T23:59:59.000Z

3

Integrated Closure and Monitoring Plan for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site  

SciTech Connect (OSTI)

This document is an integrated plan for closing and monitoring two low-level radioactive waste disposal sites at the Nevada Test Site.

Bechtel Nevada

2005-06-01T23:59:59.000Z

4

IDC Integrated Master Plan.  

SciTech Connect (OSTI)

This is the IDC Re-Engineering Phase 2 project Integrated Master Plan (IMP). The IMP presents the major accomplishments planned over time to re-engineer the IDC system. The IMP and the associate Integrated Master Schedule (IMS) are used for planning, scheduling, executing, and tracking the project technical work efforts. REVISIONS Version Date Author/Team Revision Description Authorized by V1.0 12/2014 IDC Re- engineering Project Team Initial delivery M. Harris

Clifford, David J.; Harris, James M.

2014-12-01T23:59:59.000Z

5

MITG Test Plan  

SciTech Connect (OSTI)

The plan presented is for the testing of a prototypical slice of the Modular Isotopic Thermoelectric Generator (MITG). Cross Reference T48-1.

Eck, Marshall B.

1981-08-01T23:59:59.000Z

6

Primer on gas integrated resource planning  

SciTech Connect (OSTI)

This report discusses the following topics: gas resource planning: need for IRP; gas integrated resource planning: methods and models; supply and capacity planning for gas utilities; methods for estimating gas avoided costs; economic analysis of gas utility DSM programs: benefit-cost tests; gas DSM technologies and programs; end-use fuel substitution; and financial aspects of gas demand-side management programs.

Goldman, C.; Comnes, G.A.; Busch, J.; Wiel, S. [Lawrence Berkeley Lab., CA (United States)

1993-12-01T23:59:59.000Z

7

Plan for integrated testing for NNWSI [Nevada Nuclear Waste Storage Investigations] non EQ3/6 data base portion  

SciTech Connect (OSTI)

The purposes of the Integrated Testing Task are to develop laboratory data on thermodynamic properties for actinide and fission product elements for use in the EQ3/6 geochemical modelling code; to determine the transport properties of radionuclides in the near-field environment; and develop and validate a model to describe the rate of release of radionuclides from the near-field environment. Activities to achieve the firs item have been described in the Scientific Investigation Plan for EQ3/6, where quality assurance levels were assigned to the acitivities. This Scientific Investigation Plan describes activities to achieve the second and third purposes. The information gathered in these activities will be used to assess compliance with the performance objective for the Engineered Barrier System (EBS) to control the rate of release of radionuclides if the repository license application includes part of the host rock; to provide a source term for release of radionuclides from the waste package near-field environment to the system performance assessment task for use in showing compliance with the Environmental Protection Agency requirements; and to provide a source term for release of radionculides from the waste package near-field environment to the system performance assessment task for use in doing calculations of cumulative releases of radionuclides from the repository over 100,000 years as required by the site evaluation process. 5 refs.

Oversby, V.M.

1987-05-29T23:59:59.000Z

8

Integrated Closure and Monitoring Plan for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site  

SciTech Connect (OSTI)

Bechtel Nevada (BN) manages two low-level Radioactive Waste Management Sites (RWMSs) (one site is in Area 3 and the other is in Area 5) at the Nevada Test Site (NTS) for the U.S. Department of Energy's (DOE's) National Nuclear Security Administration Nevada Operations Office (NNSA/NV). The current DOE Order governing management of radioactive waste is 435.1. Associated with DOE Order 435.1 is a Manual (DOE M 435.1-1) and Guidance (DOE G 435.1-1). The Manual and Guidance specify that preliminary closure and monitoring plans for a low-level waste (LLW) management facility be developed and initially submitted with the Performance Assessment (PA) and Composite Analysis (CA) for that facility. The Manual and Guidance, and the Disposal Authorization Statement (DAS) issued for the Area 3 RWMS further specify that the preliminary closure and monitoring plans be updated within one year following issuance of a DAS. This Integrated Closure and Monitoring Plan (ICMP) fulfills both requirements. Additional updates will be conducted every third year hereafter. This document is an integrated plan for closing and monitoring both RWMSs, and is based on guidance issued in 1999 by the DOE for developing closure plans. The plan does not follow the format suggested by the DOE guidance in order to better accommodate differences between the two RWMSs, especially in terms of operations and site characteristics. The modification reduces redundancy and provides a smoother progression of the discussion. The closure and monitoring plans were integrated because much of the information that would be included in individual plans is the same, and integration provides efficient presentation and program management. The ICMP identifies the regulatory requirements, describes the disposal sites and the physical environment where they are located, and defines the approach and schedule for both closing and monitoring the sites.

S. E. Rawlinson

2001-09-01T23:59:59.000Z

9

National conference on integrated resource planning: Proceedings  

SciTech Connect (OSTI)

Until recently, state regulators have focused most of their attention on the development of least-cost or integrated resource planning (IRP) processes for electric utilities. A number of commissions are beginning to scrutinize the planning processes of local gas distribution companies (LDCs) because of the increased control that LDCs have over their purchased gas costs (as well as the associated risks) and because of questions surrounding the role and potential of gas end-use efficiency options. Traditionally, resource planning (LDCs) has concentrated on options for purchasing and storing gas. Integrated resource planning involves the creation of a process in which supply-side and demand-side options are integrated to create a resource mix that reliably satisfies customers' short-term and long-term energy service needs at the lowest cost. As applied to gas utilities, an integrated resource plan seeks to balance cost and reliability, and should not be interpreted simply as the search for lowest commodity costs. The National Association of Regulatory Utility Commissioners' (NARUC) Energy Conservation committee asked Lawrence Berkeley Laboratory (LBL) to survey state PUCs to determine the extent to which they have undertaken least cost planning for gas utilities. The survey included the following topics: status of state PUC least-cost planning regulations and practices for gas utilities; type and scope of natural gas DSM programs in effect, including fuel substitution; economic tests and analysis methods used to evaluate DSM programs; relationship between prudency reviews of gas utility purchasing practices and integrated resource planning; key regulatory issued facing gas utilities during the next five years.

Not Available

1991-01-01T23:59:59.000Z

10

National conference on integrated resource planning: Proceedings  

SciTech Connect (OSTI)

Until recently, state regulators have focused most of their attention on the development of least-cost or integrated resource planning (IRP) processes for electric utilities. A number of commissions are beginning to scrutinize the planning processes of local gas distribution companies (LDCs) because of the increased control that LDCs have over their purchased gas costs (as well as the associated risks) and because of questions surrounding the role and potential of gas end-use efficiency options. Traditionally, resource planning (LDCs) has concentrated on options for purchasing and storing gas. Integrated resource planning involves the creation of a process in which supply-side and demand-side options are integrated to create a resource mix that reliably satisfies customers` short-term and long-term energy service needs at the lowest cost. As applied to gas utilities, an integrated resource plan seeks to balance cost and reliability, and should not be interpreted simply as the search for lowest commodity costs. The National Association of Regulatory Utility Commissioners` (NARUC) Energy Conservation committee asked Lawrence Berkeley Laboratory (LBL) to survey state PUCs to determine the extent to which they have undertaken least cost planning for gas utilities. The survey included the following topics: status of state PUC least-cost planning regulations and practices for gas utilities; type and scope of natural gas DSM programs in effect, including fuel substitution; economic tests and analysis methods used to evaluate DSM programs; relationship between prudency reviews of gas utility purchasing practices and integrated resource planning; key regulatory issued facing gas utilities during the next five years.

Not Available

1991-12-31T23:59:59.000Z

11

Integrated test schedule for buried waste integrated demonstration  

SciTech Connect (OSTI)

The Integrated Test Schedule incorporates the various schedules the Buried Waste Integrated Demonstration (BWID) supports into one document. This document contains the Federal Facilities Agreement and Consent Order schedules for the Idaho National Engineering Laboratory, Hanford Reservation, Oak Ridge Reservation, and Fernald Environmental Materials Center. Included in the Integrated Test Schedule is the Buried Waste Integrated Demonstration ``windows of opportunity`` schedule. The ``windows of opportunity`` schedule shows periods of time in which Buried Waste Integrated Demonstration Program-sponsored technology demonstrations could support key decisions in the Federal Facilities Agreement and Consent Order. Schedules for the Buried Waste Integrated Demonstration-sponsored technology task plans are categorized by technology area and divided by current fiscal year and out-year. Total estimated costs for Buried Waste Integrated Demonstration-sponsored Technology Task Plans for FY-92 through FY-97 are $74.756M.

Brown, J.T.; McDonald, J.K.

1992-05-01T23:59:59.000Z

12

Integrated test schedule for buried waste integrated demonstration  

SciTech Connect (OSTI)

The Integrated Test Schedule incorporates the various schedules the Buried Waste Integrated Demonstration (BWID) supports into one document. This document contains the Federal Facilities Agreement and Consent Order schedules for the Idaho National Engineering Laboratory, Hanford Reservation, Oak Ridge Reservation, and Fernald Environmental Materials Center. Included in the Integrated Test Schedule is the Buried Waste Integrated Demonstration windows of opportunity'' schedule. The windows of opportunity'' schedule shows periods of time in which Buried Waste Integrated Demonstration Program-sponsored technology demonstrations could support key decisions in the Federal Facilities Agreement and Consent Order. Schedules for the Buried Waste Integrated Demonstration-sponsored technology task plans are categorized by technology area and divided by current fiscal year and out-year. Total estimated costs for Buried Waste Integrated Demonstration-sponsored Technology Task Plans for FY-92 through FY-97 are $74.756M.

Brown, J.T.; McDonald, J.K.

1992-05-01T23:59:59.000Z

13

Specific test and evaluation plan  

SciTech Connect (OSTI)

The purpose of this Specific Test and Evaluation Plan (STEP) is to provide a detailed written plan for the systematic testing of modifications made to the 241-AX-B Valve Pit by the W-314 Project. The STEP develops the outline for test procedures that verify the system`s performance to the established Project design criteria. The STEP is a lower tier document based on the W-314 Test and Evaluation Plan (TEP). Testing includes Validations and Verifications (e.g., Commercial Grade Item Dedication activities), Factory Acceptance Tests (FATs), installation tests and inspections, Construction Acceptance Tests (CATs), Acceptance Test Procedures (ATPs), Pre-Operational Test Procedures (POTPs), and Operational Test Procedures (OTPs). It should be noted that POTPs are not required for testing of the transfer line addition. The STEP will be utilized in conjunction with the TEP for verification and validation.

Hays, W.H.

1998-03-20T23:59:59.000Z

14

Hydrogen Posture Plan: An Integrated Research, Development and...  

Energy Savers [EERE]

Hydrogen Posture Plan: An Integrated Research, Development and Demonstration Plan Hydrogen Posture Plan: An Integrated Research, Development and Demonstration Plan The 2006...

15

Test Series 2. 3 detailed test plan  

SciTech Connect (OSTI)

Test Series 2.3 is chronologically the second of the five sub-series of tests which comprise Test Series 2, the second major Test Series as part of the combustion research phase to be carried out at the Grimethorpe Experimental Pressurised Fluidised Bed Combustion Facility. Test Series 2.3 will consist of 700 data gathering hours which is expected to require some 1035 coal burning hours. The tests will be performed using US supplied coal and dolomite. This will be the first major series of tests on the Facility with other than the UK datum coal and dolomite. The document summarises the background to the facility and the experimental program. Described are modifications which have been made to the facility following Test Series 2.1 and a series of Screening Tests. Detailed test objectives are specified as are the test conditions for the experiments which comprise the test series. The test results will provide information on the effects of the bed temperature, excess air level, Ca/S ratio, number of coal feed lines, and combustion efficiency and sulphur retention. A significant aspect of the test series will be part load tests which will investigate the performance of the facility under conditions of turn down which simulate load following concepts specified for two combined cycle concepts, i.e., their CFCC combined cycle and a turbo charged combined cycle. The material test plan is also presented. The principal feature of the materials programme is the planned exposure of a set of static turbine blade specimens in a cascade test loop to the high temperature, high pressure flue gas. A schedule for the programme is presented as are contingency plans.

Not Available

1983-12-01T23:59:59.000Z

16

Buried Waste Integrated Demonstration Plan  

SciTech Connect (OSTI)

This document presents the plan of activities for the Buried Waste Integrated Demonstration (BWID) program which supports the environmental restoration (ER) objectives of the Department of Energy (DOE) Complex. Discussed in this plan are the objectives, organization, roles and responsibilities, and the process for implementing and managing BWID. BWID is hosted at the Idaho National Engineering Laboratory (INEL), but involves participants from throughout the DOE Complex, private industry, universities, and the international community. These participants will support, demonstrate, and evaluate a suite of advanced technologies representing a comprehensive remediation system for the effective and efficient remediation of buried waste. The processes for identifying technological needs, screening candidate technologies for applicability and maturity, selecting appropriate technologies for demonstration, field demonstrating, evaluation of results and transferring technologies to environmental restoration programs are also presented. This document further describes the elements of project planning and control that apply to BWID. It addresses the management processes, operating procedures, programmatic and technical objectives, and schedules. Key functions in support of each demonstration such as regulatory coordination, safety analyses, risk evaluations, facility requirements, and data management are presented.

Kostelnik, K.M.

1991-12-01T23:59:59.000Z

17

Vendor System Vulnerability Testing Test Plan  

SciTech Connect (OSTI)

The Idaho National Laboratory (INL) prepared this generic test plan to provide clients (vendors, end users, program sponsors, etc.) with a sense of the scope and depth of vulnerability testing performed at the INL’s Supervisory Control and Data Acquisition (SCADA) Test Bed and to serve as an example of such a plan. Although this test plan specifically addresses vulnerability testing of systems applied to the energy sector (electric/power transmission and distribution and oil and gas systems), it is generic enough to be applied to control systems used in other critical infrastructures such as the transportation sector, water/waste water sector, or hazardous chemical production facilities. The SCADA Test Bed is established at the INL as a testing environment to evaluate the security vulnerabilities of SCADA systems, energy management systems (EMS), and distributed control systems. It now supports multiple programs sponsored by the U.S. Department of Energy, the U.S. Department of Homeland Security, other government agencies, and private sector clients. This particular test plan applies to testing conducted on a SCADA/EMS provided by a vendor. Before performing detailed vulnerability testing of a SCADA/EMS, an as delivered baseline examination of the system is conducted, to establish a starting point for all-subsequent testing. The series of baseline tests document factory delivered defaults, system configuration, and potential configuration changes to aid in the development of a security plan for in depth vulnerability testing. The baseline test document is provided to the System Provider,a who evaluates the baseline report and provides recommendations to the system configuration to enhance the security profile of the baseline system. Vulnerability testing is then conducted at the SCADA Test Bed, which provides an in-depth security analysis of the Vendor’s system.b a. The term System Provider replaces the name of the company/organization providing the system being evaluated. This can be the system manufacturer, a system user, or a third party organization such as a government agency. b. The term Vendor (or Vendor’s) System replaces the name of the specific SCADA/EMS being tested.

James R. Davidson

2005-01-01T23:59:59.000Z

18

Integrated Planning and Performance Management  

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

management systems need clarification - Consolidated planning annual timetable needed for efficiency * Organizational rolesresponsibilities need alignment to defined planning...

19

Integration of Biodiversity into National Forestry Planning:...  

Open Energy Info (EERE)

Forestry Planning: An Annotated Bibliography of Web-Based Resources, Methods, Experiences, and Case Studies Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Integration...

20

INTEGRATED PLANNING: UNIVERSITY LIBRARY your library  

E-Print Network [OSTI]

INTEGRATED PLANNING: UNIVERSITY LIBRARY your library engage, enlighten, explore at library.usask.ca Transforming Library Services, Collections and Facilities: The University Library People Plan SUMMARY VERSION OVERVIEW Central themes in the library strategic plan highlight the critical importance which our people

Peak, Derek

Note: This page contains sample records for the topic "integrated test plan" 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

Materials Sciences Division Integrated Safety Management Plan  

E-Print Network [OSTI]

Materials Sciences Division Integrated Safety Management Plan Revised: February 9, 2012 Prepared by: signed Feb. 9, 2012 Rick Kelly, Facility/EH&S Manager Submitted by: signed Feb. 9, 2012 Miquel Salmeron.1 RESPONSIBILITY AND AUTHORITY THROUGH LINE MANAGEMENT............................................................5

22

Integrated Safety Management System as the Basis for Work Planning...  

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

Integrated Safety Management System as the Basis for Work Planning and Control for Research and Development Integrated Safety Management System as the Basis for Work Planning and...

23

Integrating economic costs into conservation planning  

E-Print Network [OSTI]

biodiversity losses, ecologists and conservation biologists have focused on how conservation plans affectIntegrating economic costs into conservation planning Robin Naidoo1 , Andrew Balmford2 , Paul J. Ferraro3 , Stephen Polasky4 , Taylor H. Ricketts1 and Mathieu Rouget5 1 Conservation Science Program, WWF

Vermont, University of

24

Nevada National Security Site Integrated Groundwater Sampling Plan, Revision 0  

SciTech Connect (OSTI)

The purpose of the Nevada National Security Site (NNSS) Integrated Sampling Plan (referred to herein as the Plan) is to provide a comprehensive, integrated approach for collecting and analyzing groundwater samples to meet the needs and objectives of the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) Underground Test Area (UGTA) Activity. Implementation of this Plan will provide high-quality data required by the UGTA Activity for ensuring public protection in an efficient and cost-effective manner. The Plan is designed to ensure compliance with the UGTA Quality Assurance Plan (QAP). The Plan’s scope comprises sample collection and analysis requirements relevant to assessing the extent of groundwater contamination from underground nuclear testing. This Plan identifies locations to be sampled by corrective action unit (CAU) and location type, sampling frequencies, sample collection methodologies, and the constituents to be analyzed. In addition, the Plan defines data collection criteria such as well-purging requirements, detection levels, and accuracy requirements; identifies reporting and data management requirements; and provides a process to ensure coordination between NNSS groundwater sampling programs for sampling of interest to UGTA. This Plan does not address compliance with requirements for wells that supply the NNSS public water system or wells involved in a permitted activity.

Marutzky, Sam; Farnham, Irene

2014-10-01T23:59:59.000Z

25

Integrating Timeliner and autonomous planning  

E-Print Network [OSTI]

Timeliner is used to automate tasks in a target system. Timeliner is capable of automating complex sequences of actions, but the desired actions must be planned out and understood in advance by human script-writers. This ...

Swanton, Daniel Reed

2006-01-01T23:59:59.000Z

26

Test Plan - Solids Accumulation Scouting Studies  

SciTech Connect (OSTI)

This plan documents the highlights of the Solids Accumulations Scouting Studies test; a project, from Washington River Protection Solutions (WRPS), that began on February 1, 2012. During the last 12 weeks considerable progress has been made to design and plan methods that will be used to estimate the concentration and distribution of heavy fissile solids in accumulated solids in the Hanford double-shell tank (DST) 241-AW-105 (AW-105), which is the primary goal of this task. This DST will be one of the several waste feed delivery staging tanks designated to feed the Pretreatment Facility (PTF) of the Waste Treatment and Immobilization Plant (WTP). Note that over the length of the waste feed delivery mission AW-105 is currently identified as having the most fill empty cycles of any DST feed tanks, which is the reason for modeling this particular tank. At SRNL an existing test facility, the Mixing Demonstration Tank, which will be modified for the present work, will use stainless steel particles in a simulant that represents Hanford waste to perform mock staging tanks transfers that will allow solids to accumulate in the tank heel. The concentration and location of the mock fissile particles will be measured in these scoping studies to produce information that will be used to better plan larger scaled tests. Included in these studies is a secondary goal of developing measurement methods to accomplish the primary goal. These methods will be evaluated for use in the larger scale experiments. Included in this plan are the several pretest activities that will validate the measurement techniques that are currently in various phases of construction. Aspects of each technique, e.g., particle separations, volume determinations, topographical mapping, and core sampling, have been tested in bench-top trials, as discussed herein, but the actual equipment to be employed during the full test will need evaluation after fabrication and integration into the test facility.

Duignan, M. R.; Steeper, T. J.; Steimke, J. L.; Fowley, M. D.

2012-05-10T23:59:59.000Z

27

IEEE TRANSACTIONS ON VERY LARGE SCALE INTEGRATION (VLSI) SYSTEMS, VOL. 12, NO. 12, DECEMBER 2004 1263 SOC Test Planning Using Virtual Test  

E-Print Network [OSTI]

(Cost of investing in a new ATE, also known as Capital Expenditure): Complex cores often re- quire test cost requires that once a new, expensive ATE has been purchased, its resources must be utilized-speed ATE channels to drive slower scan chains leads to an underutilization of resources, thereby resulting

Chakrabarty, Krishnendu

28

Treatability Test Plan for an In Situ Biostimulation Reducing Barrier  

SciTech Connect (OSTI)

This treatability test plan supports a new, integrated strategy to accelerate cleanup of chromium in the Hanford 100 Areas. This plan includes performing a field-scale treatability test for bioreduction of chromate, nitrate, and dissolved oxygen. In addition to remediating a portion of the plume and demonstrating reduction of electron acceptors in the plume, the data from this test will be valuable for designing a full-scale bioremediation system to apply at this and other chromium plumes at Hanford.

Truex, Michael J.; Vermeul, Vince R.; Long, Philip E.; Brockman, Fred J.; Oostrom, Mart; Hubbard, Susan; Borden, Robert C.; Fruchter, Jonathan S.

2007-07-21T23:59:59.000Z

29

Light Duty Utility Arm system pre-operational (cold test) test plan  

SciTech Connect (OSTI)

The Light Duty Utility (LDUA) Cold Test Facility, located in the Hanford 400 Area, will be used to support cold testing (pre- operational tests) of LDUA subsystems. Pre-operational testing is composed of subsystem development testing and rework activities, and integrated system qualification testing. Qualification testing will be conducted once development work is complete and documentation is under configuration control. Operational (hot) testing of the LDUA system will follow the testing covered in this plan and will be covered in a separate test plan

Bennett, K.L.

1995-10-20T23:59:59.000Z

30

Background Information for the Nevada National Security Site Integrated Sampling Plan, Revision 0  

SciTech Connect (OSTI)

This document describes the process followed to develop the Nevada National Security Site (NNSS) Integrated Sampling Plan (referred to herein as the Plan). It provides the Plan’s purpose and objectives, and briefly describes the Underground Test Area (UGTA) Activity, including the conceptual model and regulatory requirements as they pertain to groundwater sampling. Background information on other NNSS groundwater monitoring programs—the Routine Radiological Environmental Monitoring Plan (RREMP) and Community Environmental Monitoring Program (CEMP)—and their integration with the Plan are presented. Descriptions of the evaluations, comments, and responses of two Sampling Plan topical committees are also included.

Farnham, Irene; Marutzky, Sam

2014-12-01T23:59:59.000Z

31

Bayesian Optimum Planning for Accelerated Life Tests  

E-Print Network [OSTI]

Bayesian Optimum Planning for Accelerated Life Tests Yao Zhang and William Q. Meeker Dept for optimum accelerated life test planning with one accelerating variable, when the acceleration model design; Preposterior; Reliability. 1 #12;2 1 Introduction 1.1 Background and Motivation Accelerated life

32

Treatability Test Plan for an In Situ Biostimulation Reducing Barrier  

SciTech Connect (OSTI)

This treatability test plan supports a new, integrated strategy to accelerate cleanup of chromium in the 100 Areas at the Hanford Site. This plan includes performing a field-scale treatability test for bioreduction of chromate, nitrate, and dissolved oxygen. In addition to remediating a portion of the plume and demonstrating reduction of electron acceptors in the plume, the data from this test will be valuable for designing a full-scale bioremediation system to apply at this and other chromium plumes at the Hanford Site.

Truex, Michael J.; Vermeul, Vince R.; Long, Philip E.; Brockman, Fred J.; Oostrom, Mart; Hubbard, Susan; Borden, Robert C.; Fruchter, Jonathan S.

2007-10-26T23:59:59.000Z

33

Integrated Recycling Test Fuel Fabrication  

SciTech Connect (OSTI)

The Integrated Recycling Test is a collaborative irradiation test that will electrochemically recycle used light water reactor fuel into metallic fuel feedstock. The feedstock will be fabricated into a metallic fast reactor type fuel that will be irradiation tested in a drop in capsule test in the Advanced Test Reactor on the Idaho National Laboratory site. This paper will summarize the fuel fabrication activities and design efforts. Casting development will include developing a casting process and system. The closure welding system will be based on the gas tungsten arc burst welding process. The settler/bonder system has been designed to be a simple system which provides heating and controllable impact energy to ensure wetting between the fuel and cladding. The final major pieces of equipment to be designed are the weld and sodium bond inspection system. Both x-radiography and ultrasonic inspection techniques have been examine experimentally and found to be feasible, however the final remote system has not been designed. Conceptual designs for radiography and an ultrasonic system have been made.

R.S. Fielding; K.H. Kim; B. Grover; J. Smith; J. King; K. Wendt; D. Chapman; L. Zirker

2013-03-01T23:59:59.000Z

34

Geothermal drill pipe corrosion test plan  

SciTech Connect (OSTI)

Plans are presented for conducting a field test of drill pipe corrosion, comparing air and nitrogen as drilling fluids. This test will provide data for evaluating the potential of reducing geothermal well drilling costs by extending drill pipe life and reducing corrosion control costs. The 10-day test will take place during fall 1980 at the Baca Location in Sandoval County, New Mexico.

Caskey, B.C.; Copass, K.S.

1980-12-01T23:59:59.000Z

35

Operational test report for LERF Basin 242AL-44 integrity test  

SciTech Connect (OSTI)

This operational test report documents the results of LERF operational testing per operational test procedure (OTP) TFPE-WP-0231, ``LERF Basin Integrity Testing.`` The primary purpose of the OTP was to resolve test exceptions generated as a result of TFPE-WP-0184. The TOP was prepared and performed in accordance with WHC-SD-534-OTP-002, ``Operational Test Plan for the 242-A Evaporator Upgrades and the Liquid Effluent Retention Facility.`` WHC-S-086, ``Specification for Operational Testing of the Liquid Effluent Retention Facility, Basin Integrity Testing,`` identified the test requirements and acceptance criteria. The completed, signed-off test procedure is contained in Appendix A. The test log is contained in Appendix B. Section 2.1 describes all the test exceptions written during performance of the Operational Test Procedure. The test revisions generated during the testing are discussed in Section 2.2. The dispositioned test exception forms are contained in Appendix C.

Galioto, T.M.

1994-11-08T23:59:59.000Z

36

Buried Waste Integrated Demonstration Plan. Revision 1  

SciTech Connect (OSTI)

This document presents the plan of activities for the Buried Waste Integrated Demonstration (BWID) program which supports the environmental restoration (ER) objectives of the Department of Energy (DOE) Complex. Discussed in this plan are the objectives, organization, roles and responsibilities, and the process for implementing and managing BWID. BWID is hosted at the Idaho National Engineering Laboratory (INEL), but involves participants from throughout the DOE Complex, private industry, universities, and the international community. These participants will support, demonstrate, and evaluate a suite of advanced technologies representing a comprehensive remediation system for the effective and efficient remediation of buried waste. The processes for identifying technological needs, screening candidate technologies for applicability and maturity, selecting appropriate technologies for demonstration, field demonstrating, evaluation of results and transferring technologies to environmental restoration programs are also presented. This document further describes the elements of project planning and control that apply to BWID. It addresses the management processes, operating procedures, programmatic and technical objectives, and schedules. Key functions in support of each demonstration such as regulatory coordination, safety analyses, risk evaluations, facility requirements, and data management are presented.

Kostelnik, K.M.

1991-12-01T23:59:59.000Z

37

EMERGENCY RESPONSE PLAN DEVINE TEST SITE  

E-Print Network [OSTI]

HSE MANUAL EMERGENCY RESPONSE PLAN DEVINE TEST SITE EXPLORATION GEOPHYSICS LAB FIELD SITE MEDINA LIST OF CONTACTS ­ SITE MANAGERS AND EMERGENCY RESPONSE PAGE 20 CERTIFICATE OF COMPLETION PAGE 21 2 #12 is too trivial. The Bureau's test-site manager is responsible for orienting you previous to your arrival

Texas at Austin, University of

38

Planning integration FY 1995 Multi-Year Program Plan (MYPP)/Fiscal Year Work Plan (FYWP)  

SciTech Connect (OSTI)

This Multi-Year Program Plan (MYPP) for the Planning Integration Program, Work Breakdown structure (WBS) Element 1.8.2, is the primary management tool to document the technical, schedule, and cost baseline for work directed by the US Department of Energy (DOE), Richland Operations Office (RL). As an approved document, it establishes a binding agreement between RL and the performing contractors for the work to be performed. It was prepared by the Westinghouse Hanford Company (WHC) and the Pacific Northwest Laboratory (PNL). This MYPP provides a picture from fiscal year 1995 through FY 2001 for the Planning Integration Program. The MYPP provides a window of detailed information for the first three years. It also provides `execution year` work plans. The MYPP provides summary information for the next four years, documenting the same period as the Activity Data Sheets.

Not Available

1994-09-01T23:59:59.000Z

39

The Modified Sudden Death Test: Planning Life Tests with a Limited Number of Test Positions  

E-Print Network [OSTI]

The Modified Sudden Death Test: Planning Life Tests with a Limited Number of Test Positions Francis for Nondestructive Evaluation Iowa State University Ames, IA 50011 ABSTRACT: We present modified sudden death test (MSDT) plans to address the problem of limited testing positions in life tests. A single MSDT involves

40

The Modi ed Sudden Death Test: Planning Life Tests with a Limited Number of Test Positions  

E-Print Network [OSTI]

The Modi ed Sudden Death Test: Planning Life Tests with a Limited Number of Test Positions Francis for Nondestructive Evaluation Iowa State University Ames, IA 50011 ABSTRACT: We present modi ed sudden death test (MSDT) plans to address the problem of limited testing positions in life tests. A single MSDT involves

Note: This page contains sample records for the topic "integrated test plan" 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

Integration of Safety Culture Attributes into EFCOG Work Planning...  

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

Work Planning and Control Guidance Document May 15, 2013 Presenters: Steele Coddington, NSTec, Las Vegas, and John McDonald, WRPS, Hanford Topics Covered: Integration of Safety...

42

Spent Nuclear Fuel project integrated safety management plan  

SciTech Connect (OSTI)

This document is being revised in its entirety and the document title is being revised to ``Spent Nuclear Fuel Project Integrated Safety Management Plan.

Daschke, K.D.

1996-09-17T23:59:59.000Z

43

UMass Amherst Campus Planning INTEGRATED DESIGN BUILDING  

E-Print Network [OSTI]

#12;UMass Amherst Campus Planning · Hills House · IDB Program Vision · IDB;UMass Amherst Campus Planning Hills House · Exterior cladding failure · Poor airDvity and ecological awareness. #12;UMass Amherst Campus Planning Program Spaces · Studios

Massachusetts at Amherst, University of

44

AGR-1 Irradiation Experiment Test Plan  

SciTech Connect (OSTI)

This document presents the current state of planning for the AGR-1 irradiation experiment, the first of eight planned irradiations for the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. The objectives of the AGR-1 experiment are: 1. To gain experience with multi-capsule test train design, fabrication, and operation with the intent to reduce the probability of capsule or test train failure in subsequent irradiation tests. 2. To irradiate fuel produced in conjunction with the AGR fuel process development effort. 3. To provide data that will support the development of an understanding of the relationship between fuel fabrication processes, fuel product properties, and irradiation performance. In order to achieve the test objectives, the AGR-1 experiment will be irradiated in the B-10 position of the Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL). The test will contain six independently controlled and monitored capsules. Each capsule will contain a single type, or variant, of the AGR coated fuel. The irradiation is planned for about 700 effective full power days (approximately 2.4 calendar years) with a time-averaged, volume-average temperature of approximately 1050 °C. Average fuel burnup, for the entire test, will be greater than 17.7 % FIMA, and the fuel will experience fast neutron fluences between 2.4 and 4.5 x 1025 n/m2 (E>0.18 MeV).

John T. Maki

2009-10-01T23:59:59.000Z

45

Planning Accelerated Destructive Degradation Test with Competing Risks  

E-Print Network [OSTI]

Planning Accelerated Destructive Degradation Test with Competing Risks Ying Shi Dept. of Statistics University Ames, IA 50011 wqmeeker@iastate.edu Abstract Accelerated destructive degradation tests (ADDTs plan specifies the test conditions of accelerating variables, running time, and the corresponding

46

GEOCHEMICAL TESTING AND MODEL DEVELOPMENT - RESIDUAL TANK WASTE TEST PLAN  

SciTech Connect (OSTI)

This Test Plan describes the testing and chemical analyses release rate studies on tank residual samples collected following the retrieval of waste from the tank. This work will provide the data required to develop a contaminant release model for the tank residuals from both sludge and salt cake single-shell tanks. The data are intended for use in the long-term performance assessment and conceptual model development.

CANTRELL KJ; CONNELLY MP

2010-03-09T23:59:59.000Z

47

Test Methods Standing Technical Committee Strategic Plan - February...  

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

Strategic Plan - February 2012 Test Methods Standing Technical Committee Strategic Plan - February 2012 This document outlines gaps, needs, and opportunities identified by the...

48

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

49

Test Plan: WIPP bin-scale CH TRU waste tests  

SciTech Connect (OSTI)

This WIPP Bin-Scale CH TRU Waste Test program described herein will provide relevant composition and kinetic rate data on gas generation and consumption resulting from TRU waste degradation, as impacted by synergistic interactions due to multiple degradation modes, waste form preparation, long-term repository environmental effects, engineered barrier materials, and, possibly, engineered modifications to be developed. Similar data on waste-brine leachate compositions and potentially hazardous volatile organic compounds released by the wastes will also be provided. The quantitative data output from these tests and associated technical expertise are required by the WIPP Performance Assessment (PA) program studies, and for the scientific benefit of the overall WIPP project. This Test Plan describes the necessary scientific and technical aspects, justifications, and rational for successfully initiating and conducting the WIPP Bin-Scale CH TRU Waste Test program. This Test Plan is the controlling scientific design definition and overall requirements document for this WIPP in situ test, as defined by Sandia National Laboratories (SNL), scientific advisor to the US Department of Energy, WIPP Project Office (DOE/WPO). 55 refs., 16 figs., 19 tabs.

Molecke, M.A.

1990-08-01T23:59:59.000Z

50

Accelerated Destructive Degradation Test Planning Dept. of Statistics  

E-Print Network [OSTI]

Accelerated Destructive Degradation Test Planning Ying Shi Dept. of Statistics Iowa State Ames, IA 50011 wqmeeker@iastate.edu Abstract Accelerated Destructive Degradation Tests (ADDTs) provide reliability information quickly. An ADDT plan specifies factor level combinations of an accelerating variable

51

Phase Startup Initiative Phases 3 and 4 Test Plan and Test Specification ( OCRWM)  

SciTech Connect (OSTI)

Construction for the Spent Nuclear Fuel (SNF) Project facilities is continuing per the Level III Baseline Schedule, and installation of the Fuel Retrieval System (FRS) and Integrated Water Treatment System (IWTS) in K West Basin is now complete. In order to accelerate the project, a phased start up strategy to initiate testing of the FRS and IWTS early in the overall project schedule was proposed (Williams 1999). Wilkinson (1999) expands the definition of the original proposal into four functional testing phases of the Phased Startup Initiative (PSI). Phases 1 and 2 are based on performing functional tests using dummy fuel. This test plan provides overall guidance for Phase 3 and 4 tests, which are performed using actual irradiated N fuel assemblies. The overall objective of the Phase 3 and 4 testing is to verify how the FRS and IWTS respond while processing actual fuel. Conducting these tests early in the project schedule will allow identification and resolution of equipment and process problems before they become activities on the start-up critical path. The specific objectives of this test plan are to: Define the Phase 3 and 4 test scope for the FRS and IWTS; Provide detailed test requirements that can be used to write the specific test procedures; Define data required and measurements to be taken. Where existing methods to obtain these do not exist, enough detail will be provided to define required additional equipment; and Define specific test objectives and acceptance criteria.

PAJUNEN, A.L.; LANGEVIN, M.J.

2000-08-07T23:59:59.000Z

52

Integrated Planning and Management for Urban Water Supplies  

E-Print Network [OSTI]

Positions for Water Supply Reliability ................................. 15 4 Shortage Management Modeling.2: Diagram of Water Supply Reliability Model Structure ..................49 5.3: Steps Used in ShortageIntegrated Planning and Management for Urban Water Supplies Considering Multiple Uncertainties Jay

Pasternack, Gregory B.

53

Integrated Program of Experimental Diagnostics at the NNSS: An Integrated, Prioritized Work Plan for Diagnostic Development and Maintenance and Supporting Capability  

SciTech Connect (OSTI)

This Integrated Program of Experimental Diagnostics at the NNSS is an integrated prioritized work plan for the Nevada National Security Site (NNSS), formerly the Nevada Test Site (NTS), program that is independent of individual National Security Enterprise Laboratories’ (Labs) requests or specific Subprograms being supported. This prioritized work plan is influenced by national priorities presented in the Predictive Capability Framework (PCF) and other strategy documents (Primary and Secondary Assessment Technologies Plans and the Plutonium Experiments Plan). This document satisfies completion criteria for FY 2010 MRT milestone #3496: Document an integrated, prioritized work plan for diagnostic development, maintenance, and supporting capability. This document is an update of the 3?year NNSS plan written a year ago, September 21, 2009, to define and understand Lab requests for diagnostic implementation. This plan is consistent with Lab interpretations of the PCF, Primary Assessment Technologies, and Plutonium Experiment plans.

NSTec Mission and Projects Division

2010-09-30T23:59:59.000Z

54

Integrated Resource Planning: A Dialogue with ELCON  

E-Print Network [OSTI]

the building of generating units. Planning decisions would now include alternative energy sources 2 and demand side management. Also very important in the IRP process is the evaluation of external impacts of any planning decision with a special focus... and demand resources in electricity markets. In this paper we provide a definition of that concept and discuss two of its main features: Demand-side Management programs and environmental externalities. We also examine a number of positions taken by ELCON...

Treadway, N.; Torrent, G.

55

Vitrification Facility integrated system performance testing report  

SciTech Connect (OSTI)

This report provides a summary of component and system performance testing associated with the Vitrification Facility (VF) following construction turnover. The VF at the West Valley Demonstration Project (WVDP) was designed to convert stored radioactive waste into a stable glass form for eventual disposal in a federal repository. Following an initial Functional and Checkout Testing of Systems (FACTS) Program and subsequent conversion of test stand equipment into the final VF, a testing program was executed to demonstrate successful performance of the components, subsystems, and systems that make up the vitrification process. Systems were started up and brought on line as construction was completed, until integrated system operation could be demonstrated to produce borosilicate glass using nonradioactive waste simulant. Integrated system testing and operation culminated with a successful Operational Readiness Review (ORR) and Department of Energy (DOE) approval to initiate vitrification of high-level waste (HLW) on June 19, 1996. Performance and integrated operational test runs conducted during the test program provided a means for critical examination, observation, and evaluation of the vitrification system. Test data taken for each Test Instruction Procedure (TIP) was used to evaluate component performance against system design and acceptance criteria, while test observations were used to correct, modify, or improve system operation. This process was critical in establishing operating conditions for the entire vitrification process.

Elliott, D.

1997-05-01T23:59:59.000Z

56

100 Area soil washing treatability test plan  

SciTech Connect (OSTI)

This test plan describes specifications, responsibilities, and general methodology for conducting a soil washing treatability study as applied to source unit contamination in the 100 Area. The objective ofthis treatability study is to evaluate the use of physical separation systems and chemical extraction methods as a means of separating chemically and radioactively contaminated soil fractions from uncontaminated soil fractions. The purpose of separating these fractions is to minimize the volume of soil requiring permanent disposal. It is anticipated that this treatability study will be performed in two phases of testing, a remedy screening phase and a remedy selection phase. The remedy screening phase consists of laboratory- and bench-scale studies performed by Battelle Pacific Northwest laboratories (PNL) under a work order issued by Westinghouse Hanford Company (Westinghouse Hanford). This phase will be used to provide qualitative evaluation of the potential effectiveness of the soil washing technology. The remedy selection phase, consists of pilot-scale testing performed under a separate service contract to be competitively bid under Westinghouse Hanford direction. The remedy selection phase will provide data to support evaluation of the soil washing technology in future feasibility studies for Interim Remedial Measures (IRMs) or final operable unit (OU) remedies. Performance data from these tests will indicate whether applicable or relevant and appropriate requirements (ARARs) or cleanup goals can be met at the site(s) by application of soil washing. The remedy selection tests wig also allow estimation of costs associated with implementation to the accuracy required for the Feasibility Study.

Not Available

1993-03-01T23:59:59.000Z

57

Design of Integrated Laboratory and Heavy-Duty Emissions Testing...  

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

of Integrated Laboratory and Heavy-Duty Emissions Testing Center Design of Integrated Laboratory and Heavy-Duty Emissions Testing Center Both simulated and actual diesel emissions...

58

Develop Standard Method of Test for Integrated Heat Pump - 2013...  

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

Develop Standard Method of Test for Integrated Heat Pump - 2013 Peer Review Develop Standard Method of Test for Integrated Heat Pump - 2013 Peer Review Emerging Technologies...

59

MO. IU~Y."U. : : I ~ Test Plans for Aceeptanc e I-..;A;.;;.;T;.;M~-,.;;5;.;4;.;;8;.......___....;;A-..___  

E-Print Network [OSTI]

of A the experiment at BxA and ·integration into ALSEP. This document covers the Engineering Model and prototype tests are applicable to this test plan to the extent referenced h.erein. l. Interface Control Specification prepared to document test plans for acceptance tests on the SIDE/CCGE Engineering Model. These plans cover

Rathbun, Julie A.

60

AGC-1 Irradiation Experiment Test Plan  

SciTech Connect (OSTI)

The Advanced Graphite Capsule (AGC) irradiation test program supports the acquisition of irradiated graphite performance data to assist in the selection of the technology to be used for the VHTR. Six irradiations are planned to investigate compressive creep in graphite subjected to a neutron field and obtain irradiated mechanical properties of vibrationally molded, extruded, and iso-molded graphites for comparison. The experiments will be conducted at three temperatures: 600, 900, and 1200°C. At each temperature, two different capsules will be irradiated to different fluence levels, the first from 0.5 to 4 dpa and the second from 4 to 7 dpa. AGC-1 is the first of the six capsules designed for ATR and will focus on the prismatic fluence range.

R. L. Bratton

2006-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "integrated test plan" 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

Nevada Test Site Resource Management Plan  

SciTech Connect (OSTI)

The Nevada Test Site (NTS) Resource Management Plan (RMP) describes the NTS Stewardship Mission and how its accomplishment will preserve the resources of the ecoregion while accomplishing the objectives of the mission. The NTS Stewardship Mission is to manage the land and facilities at the NTS as a unique and valuable national resource. The RMP has defined goals for twelve resource areas based on the principles of ecosystem management. These goals were established using an interdisciplinary team of DOE/NV resource specialists with input from surrounding land managers, private parties, and representatives of Native American governments. The overall goal of the RMP is to facilitate improved NTS land use management decisions within the Great Basin and Mojave Desert ecoregions.

NONE

1998-12-01T23:59:59.000Z

62

Integrated Planning for Water and Energy Systems  

E-Print Network [OSTI]

Policy 2. Energy Intensity of Water 3. Water Intensity of Energy 1. Integrated Energy and Water Policy 2. Energy Intensity of Water 3. Water Intensity of Energy #12;Total Water Withdrawals, 2000Total Water at Edmonston #12;Energy Intensity of WaterEnergy Intensity of Water Energy intensity, or embedded energy

Keller, Arturo A.

63

UML-Based Integration Testing Jean Hartmann  

E-Print Network [OSTI]

UML-Based Integration Testing Jean Hartmann Siemens Corporate Research 755 College Road East Princeton NJ 08540 ++1 609 734 3361 jhartmann@scr.siemens.com Claudio Imoberdorf Siemens Corporate Research 755 College Road East Princeton NJ 08540 ++1 609 734 3688 claudio@scr.siemens.com Michael Meisinger

64

Fusing Integration Test Management with Change Management  

E-Print Network [OSTI]

- 1 - Infuse: Fusing Integration Test Management with Change Management Gail E. Kaiser* Dewayne E, NJ 07974 Murray Hill, NJ 07974 Infuse is an experimental software development environment focusing the change set into the baseline. We have previously described how Infuse enforces static consistency at each

Perry, Dewayne E.

65

Integrated safeguards and security management plan  

SciTech Connect (OSTI)

Berkeley Lab is committed to scientific excellence and stewardship of its assets. While security principles apply to all work performed at the Laboratory, their implementation is flexible. Berkeley Lab adheres to the following principles: Line management owns security; Security roles and responsibilities are clearly defined and communicated; Security functions are integrated; An open environment supports the Laboratory's Mission; The security program must support the scientific and operational missions of the Laboratory and must be value added; and Security controls are tailored to individual and facility requirements.

Bowen, Sue, editor

2001-04-16T23:59:59.000Z

66

Integrated Waste Feed Delivery Plan - Hanford Site  

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 and NovelFEG-SEM with EDAXforHome IntegratedOfficial

67

Design plan for development of the worldwide port system (WPS) regional integrated cargo database (ICDB)  

SciTech Connect (OSTI)

The Worldwide Port System (WPS) Regional Integrated Cargo Database (ICDB) is a major military computer system that provides visibility over international cargo. Development started in early 1993 and implementation began on the West Coast in August of 1995. The Design Plan coordinated developmental efforts for the ICDB and its related processes. A Design Plan was especially important because the ICDB was developed at multiple sites by Oak Ridge National Laboratory and Military Traffic Management Command personnel. A Design Plan was essential to ensure that a consistent design was maintained throughout all modules, that functional and technical requirements were accomplished, that all components and processes worked together successfully, and that the development schedule was met. This plan described ICDB modules and tasks within each module. It documented responsibilities and dependencies by module and presented a schedule for development, testing, and integration.

Truett, L.F.; Rollow, J.P.; Shipe, P.C.

1995-11-01T23:59:59.000Z

68

Visopt ShopFloor System: Integrating Planning into Production Scheduling  

E-Print Network [OSTI]

Visopt ShopFloor System: Integrating Planning into Production Scheduling Roman Barták Charles, the first machine pre-processes the item (3 time units) that is finished in the second machine (additional 3 in parallel and a worker is required (left) or via a serial production when the item is pre- processed

Bartak, Roman

69

Test plan for BWID Phase 2 electric arc melter vitrification tests  

SciTech Connect (OSTI)

This test plan describes the Buried Waste Integrated Demonstration (BWID), Phase 2, electric arc melter, waste treatment evaluation tests to be performed at the US Bureau of Mines (USBM) Albany Research Center. The BWID Arc Melter Vitrification Project is being conducted to evaluate and demonstrate existing industrial arc melter technology for thermally treating mixed transuranic-contaminated wastes and soils. Phase 1 baseline tests, performed during fiscal year 1993 at the USBM, were conducted on waste feeds representing incinerated buried mixed wastes and soils. In Phase 2, surrogate feeds will be processed that represent actual as-retrieved buried wastes from the Idaho National Engineering Laboratory`s Subsurface Disposal Area at the Radioactive Waste Management Complex.

Soelberg, N.R.; Turner, P.C.; Oden, L.L.; Anderson, G.L.

1994-10-01T23:59:59.000Z

70

Plan and Strategy for ITER Blanket Testing in Japan  

SciTech Connect (OSTI)

The Fusion Council of Japan has established the long-term program for the development of blanket in 1999. In the program, the solid breeder blanket was selected as the primary candidate blanket of the fusion power demonstration plant in Japan, while liquid breeder blankets and high temperature solid breeder blanket have been identified as the attractive advanced blanket. Japan Atomic Energy Research Institute (JAERI) is leading the development of solid breeder blankets, while, universities and National Institute for Fusion Science (NIFS) are developing the advanced blankets for potential options of the fusion power demonstration plant and commercial power plants. ITER blanket module testing is regarded as one of the most important milestones, by which integrity of candidate blanket design is qualified for the fusion power demonstration plant, together with material irradiation data by International Fusion Material Irradiation Facility (IFMIF). Japan is investigating the possibility of testing all types of blankets under TBWG framework with both of JAERI and universities/NIFS involvements. This paper presents a plan and strategy for the development of test blanket modules and ITER blanket module testing in Japan.

Enoeda, Mikio [Japan Atomic Energy Research Institute (Japan); Akiba, Masato [Japan Atomic Energy Research Institute (Japan); Tanaka, Satoru [University of Tokyo (Japan); Shimizu, Akihiko [Kyushu University (Japan); Hasegawa, Akira [Tohoku University (Japan); Konishi, Satoshi [Kyoto University (Japan); Kimura, Akihiko [Kyoto University (Japan); Kohyama, Akira [Kyoto University (Japan); Sagara, Akio [National Institute of Fusion Science (Japan); Muroga, Takeo [National Institute of Fusion Science (Japan)

2005-05-15T23:59:59.000Z

71

Bayesian Methods for Accelerated Destructive Degradation Test Planning  

E-Print Network [OSTI]

Bayesian Methods for Accelerated Destructive Degradation Test Planning Ying Shi Dept. of Statistics University Ames, IA 50011 wqmeeker@iastate.edu Abstract Accelerated Destructive Degradation Tests (ADDTs methods for ADDT planning under a class of nonlinear degradation models with one accelerating variable. We

72

Methods For Planning Accelerated Repeated Measures Degradation Tests  

E-Print Network [OSTI]

Methods For Planning Accelerated Repeated Measures Degradation Tests Brian P. Weaver Statistical of Statistics Iowa State University Ames, IA 50010 wqmeeker@iastate.edu September 3, 2013 Abstract Accelerated-variable accelerated repeated measures degradation test plan when the (possibly transformed) degradation is linear

73

Parking and routing information system phase 1 evaluation -- Individual evaluation test plans  

SciTech Connect (OSTI)

A parking and routing information system (PARIS) is being designed and deployed at a test site on the Mountain Home Veterans Administration campus in Johnson City, Tennessee using three sensor technologies. The purpose of the PARIS project is to demonstrate innovative integration of vehicle sensing technologies with parking management strategies to improve mobility and relieve congestion associated with a growing medical/technology complex. This technical memorandum presents the four individual evaluation test plans, System Performance Individual Evaluation Test Plan, User Acceptance Individual Evaluation Test Plan, Institutional and Business Issues Individual Evaluation Test Plan, and Transportation Systems Individual Evaluation Test Plan, which were developed to support ORNL`s responsibilities and functions during the four studies. The plans define the level of effort required to satisfy the data collection, processing, and analysis requirements for the assessment of the system performance, user acceptance, institutional and business issues, and transportation systems components of the PARIS phase 1 evaluation. Each plan is divided into three subsections: executive summary, detailed study design, and study management.

Carter, R.J.

1997-04-01T23:59:59.000Z

74

Nevada Test Site Resource Management Plan: Annual summary, January 2000  

SciTech Connect (OSTI)

The Nevada Test Site Resource Management Plan published in December of 1998 (DOE/NV--518) describes the Nevada Test Site stewardship mission and how its accomplishment will preserve the resources of the ecoregion while accomplishing the objectives of the mission. As part of the Nevada Test Site Resource Management Plan, DOE Nevada Operations Office has committed to perform and publish an annual summary review of DOE Nevada Operations' stewardship of the Nevada Test Site. This annual summary includes a description of progress made toward the goals of the Nevada Test Site Resource Management Plan, pertinent monitoring data, actions that were taken to adapt to changing conditions, and any other changes to the Nevada Test Site Resource Management Plan.

NONE

2000-01-01T23:59:59.000Z

75

Integrated Lateral Flow Test Strip with Electrochemical Sensor...  

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

Lateral Flow Test Strip with Electrochemical Sensor for Quantification of Phosphorylated Cholinesterase: Biomarker of Integrated Lateral Flow Test Strip with Electrochemical Sensor...

76

High Burnup Dry Storage Cask Research and Development Project, Final Test Plan  

SciTech Connect (OSTI)

EPRI is leading a project team to develop and implement the first five years of a Test Plan to collect data from a SNF dry storage system containing high burnup fuel.12 The Test Plan defined in this document outlines the data to be collected, and the storage system design, procedures, and licensing necessary to implement the Test Plan.13 The main goals of the proposed test are to provide confirmatory data14 for models, future SNF dry storage cask design, and to support license renewals and new licenses for ISFSIs. To provide data that is most relevant to high burnup fuel in dry storage, the design of the test storage system must mimic real conditions that high burnup SNF experiences during all stages of dry storage: loading, cask drying, inert gas backfilling, and transfer to the ISFSI for multi-year storage.15 Along with other optional modeling, SETs, and SSTs, the data collected in this Test Plan can be used to evaluate the integrity of dry storage systems and the high burnup fuel contained therein over many decades. It should be noted that the Test Plan described in this document discusses essential activities that go beyond the first five years of Test Plan implementation.16 The first five years of the Test Plan include activities up through loading the cask, initiating the data collection, and beginning the long-term storage period at the ISFSI. The Test Plan encompasses the overall project that includes activities that may not be completed until 15 or more years from now, including continued data collection, shipment of the Research Project Cask to a Fuel Examination Facility, opening the cask at the Fuel Examination Facility, and examining the high burnup fuel after the initial storage period.

none,

2014-02-27T23:59:59.000Z

77

Integrated Renewable Hydrogen Utility System (IRHUS) business plan  

SciTech Connect (OSTI)

This business plan is for a proposed legal entity named IRHUS, Inc. which is to be formed as a subsidiary of Energy Partners, L.C. (EP) of West Palm Beach, Florida. EP is a research and development company specializing in hydrogen proton exchange membrane (PEM) fuel cells and systems. A fuel cell is an engine with no moving parts that takes in hydrogen and produces electricity. The purpose of IRHUS, Inc. is to develop and manufacture a self-sufficient energy system based on the fuel cell and other new technology that produces hydrogen and electricity. The product is called the Integrated renewable Hydrogen utility System (IRHUS). IRHUS, Inc. plans to start limited production of the IRHUS in 2002. The IRHUS is a unique product with an innovative concept in that it provides continuous electrical power in places with no electrical infrastructure, i.e., in remote and island locations. The IRHUS is a zero emissions, self-sufficient, hydrogen fuel generation system that produces electricity on a continuous basis by combining any renewable power source with hydrogen technology. Current plans are to produce a 10 kilowatt IRHUS MP (medium power). Future plans are to design and manufacture IRHUS models to provide power for a variety of power ranges for identified attractive market segments. The technological components of the IRHUS include an electrolyzer, hydrogen and oxygen storage subsystems, fuel cell system, and power control system. The IRHUS product is to be integrated with a variety of renewable energy technologies. 5 figs., 10 tabs.

NONE

1999-03-01T23:59:59.000Z

78

Test plan for the 34 meter vertical axis wind turbine test bed located at Bushland, Texas  

SciTech Connect (OSTI)

A plan is presented for the testing and evaluation of a new 500 kw vertical axis wind turbine test bed. The plan starts with the initial measurements made during construction, proceeds through evaluation of the design, the development of control methods, and finally to the test bed phase where new concepts are evaluated and in-depth studies are performed.

Stephenson, W.A.

1986-12-01T23:59:59.000Z

79

Long-term corrosion testing plan.  

SciTech Connect (OSTI)

This document describes the testing and facility requirements to support the Yucca Mountain Project long-term corrosion testing program. The purpose of this document is to describe a corrosion testing program that will (a) reduce model uncertainty and variability, (b) reduce the reliance upon overly conservative assumptions, and (c) improve model defensibility. Test matrices were developed for 17 topical areas (tasks): each matrix corresponds to a specific test activity that is a subset of the total work performed in a task. A future document will identify which of these activities are considered to be performance confirmation activities. Detailed matrices are provided for FY08, FY09 and FY10 and rough order estimates are provided for FY11-17. Criteria for the selection of appropriate test facilities were developed through a meeting of Lead Lab and DOE personnel on October 16-17, 2007. These criteria were applied to the testing activities and recommendations were made for the facility types appropriate to carry out each activity. The facility requirements for each activity were assessed and activities were identified that can not be performed with currently available facilities. Based on this assessment, a total of approximately 10,000 square feet of facility space is recommended to accommodate all future testing, given that all testing is consolidated to a single location. This report is a revision to SAND2008-4922 to address DOE comments.

Wall, Frederick Douglas; Brown, Neil R. (Los Alamos National Laboratory, Los Alamos, NM)

2009-02-01T23:59:59.000Z

80

SAPHIRE 8 Software Acceptance Test Plan  

SciTech Connect (OSTI)

This document describe & report the overall SAPHIRE 8 Software acceptance test paln to offically release the SAPHIRE version 8 software to the NRC custoer for distribution.

Ted S. Wood; Curtis L. Smith

2009-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "integrated test plan" 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

New Developments in Planning Accelerated Life Tests.  

E-Print Network [OSTI]

??Accelerated life tests (ALTs) are often used to make timely assessments of the life time distribution of materials and components. The goal of many ALTs… (more)

Ma, Haiming

2009-01-01T23:59:59.000Z

82

PROPERTIES IMPORTANT TO MIXING FOR WTP LARGE SCALE INTEGRATED TESTING  

SciTech Connect (OSTI)

Large Scale Integrated Testing (LSIT) is being planned by Bechtel National, Inc. to address uncertainties in the full scale mixing performance of the Hanford Waste Treatment and Immobilization Plant (WTP). Testing will use simulated waste rather than actual Hanford waste. Therefore, the use of suitable simulants is critical to achieving the goals of the test program. External review boards have raised questions regarding the overall representativeness of simulants used in previous mixing tests. Accordingly, WTP requested the Savannah River National Laboratory (SRNL) to assist with development of simulants for use in LSIT. Among the first tasks assigned to SRNL was to develop a list of waste properties that matter to pulse-jet mixer (PJM) mixing of WTP tanks. This report satisfies Commitment 5.2.3.1 of the Department of Energy Implementation Plan for Defense Nuclear Facilities Safety Board Recommendation 2010-2: physical properties important to mixing and scaling. In support of waste simulant development, the following two objectives are the focus of this report: (1) Assess physical and chemical properties important to the testing and development of mixing scaling relationships; (2) Identify the governing properties and associated ranges for LSIT to achieve the Newtonian and non-Newtonian test objectives. This includes the properties to support testing of sampling and heel management systems. The test objectives for LSIT relate to transfer and pump out of solid particles, prototypic integrated operations, sparger operation, PJM controllability, vessel level/density measurement accuracy, sampling, heel management, PJM restart, design and safety margin, Computational Fluid Dynamics (CFD) Verification and Validation (V and V) and comparison, performance testing and scaling, and high temperature operation. The slurry properties that are most important to Performance Testing and Scaling depend on the test objective and rheological classification of the slurry (i.e., Newtonian or non-Newtonian). The most important properties for testing with Newtonian slurries are the Archimedes number distribution and the particle concentration. For some test objectives, the shear strength is important. In the testing to collect data for CFD V and V and CFD comparison, the liquid density and liquid viscosity are important. In the high temperature testing, the liquid density and liquid viscosity are important. The Archimedes number distribution combines effects of particle size distribution, solid-liquid density difference, and kinematic viscosity. The most important properties for testing with non-Newtonian slurries are the slurry yield stress, the slurry consistency, and the shear strength. The solid-liquid density difference and the particle size are also important. It is also important to match multiple properties within the same simulant to achieve behavior representative of the waste. Other properties such as particle shape, concentration, surface charge, and size distribution breadth, as well as slurry cohesiveness and adhesiveness, liquid pH and ionic strength also influence the simulant properties either directly or through other physical properties such as yield stress.

Koopman, D.; Martino, C.; Poirier, M.

2012-04-26T23:59:59.000Z

83

Nevada Test Site Treatment Plan. Revision 2  

SciTech Connect (OSTI)

Treatment Plans (STPS) are required for facilities at which the US Department of Energy (DOE) or stores mixed waste, defined by the Federal Facility Compliance Act (FFCAct) as waste containing both a hazardous waste subject to the Resource Conservation and Recovery Act and a radioactive material subject to the Atomic Energy Act. On April 6, 1993, DOE published a Federal Register notice (58 FR 17875) describing its proposed process for developing the STPs in three phases including a Conceptual, a Draft, and a Proposed Site Treatment Plan (PSTP). All of the DOE Nevada Operations Office STP iterations have been developed with the state of Nevada`s input. The options and schedules reflect a ``bottoms-up`` approach and have been evaluated for impacts on other DOE sites, as well as impacts to the overall DOE program. Changes may have occurred in the preferred option and associated schedules between the PSTP, which was submitted to the state of Nevada and US Environmental Protection Agency April 1995, and the Final STP (hereafter referred to as the STP) as treatment evaluations progressed. The STP includes changes that have occurred since the submittal of the PSTP as a result of state-to-state and DOE-to-state discussions.

NONE

1996-03-01T23:59:59.000Z

84

Sludge stabilization boat material test plan  

SciTech Connect (OSTI)

This document provides instructions for testing different types of potential boat materials in the HC-21C muffle furnace process. The boats must withstand corrosive environments at up to 1000 degrees C.

De Vries, M.L.

1995-04-05T23:59:59.000Z

85

NCRF gun status and test plan  

SciTech Connect (OSTI)

Summary of this presentation are: (1) NCRF injector has achieved >7MV/m average gradients; (2) RGA trace shows little water in cathode cell; (3) NCRF injector has produced electron beams; (4) Dark current can be reduced with solenoid magnetic field; (5) An RF window failed at RF power above 800kW; (6) Beam tests will be performed with both RLWG (each exposed to 500kW of RF power); and (7) Beam tests will use CsK{sub 2}Sb photocathodes fabricated using low-temperature alkali sources.

Nguyen, Dinh C [Los Alamos National Laboratory

2011-01-20T23:59:59.000Z

86

IFE chamber technology testing program in NIF and chamber development test plan  

SciTech Connect (OSTI)

Issues concerning chamber technology testing program in NIF involving: criteria for evaluation/prioritization of experiments, engineering scaling requirements for test article design and material selection and R and D plan prior to NIF testing were addressed in this paper. In order to maximize the benefits of testing program in NIF, the testing in NIF should provide the experimental data relevant to DEMO design choice or to DEMO design predictive capability by utilizing engineering scaling test article designs. Test plans were developed for 2 promising chamber design concepts. Early testing in non-fusion/non-ignition prior to testing in ignition facility serves a critical role in chamber R and D test plans in order to reduce the risks and costs of the more complex experiments in NIF.

Abdou, M.A. [Univ. of California, Los Angeles, CA (United States)

1995-12-31T23:59:59.000Z

87

acceptance test plan: Topics by E-print Network  

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

acceptance test plan First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 G4Beamline Acceptance Tests Chris...

88

Experimental Test Plan DOE Tidal and River Reference Turbines  

SciTech Connect (OSTI)

Our aim is to provide details of the experimental test plan for scaled model studies in St. Anthony Falls Laboratory (SAFL) Main Channel at the University of Minnesota, including a review of study objectives, descriptions of the turbine models, the experimental set-up, instrumentation details, instrument measurement uncertainty, anticipated experimental test cases, post-processing methods, and data archiving for model developers.

Neary, Vincent S [ORNL; Hill, Craig [St. Anthony Falls Laboratory, 2 Third Avenue SE, Minneapolis, MN 55414; Chamorro, Leonardo [St. Anthony Falls Laboratory, 2 Third Avenue SE, Minneapolis, MN 55414; Gunawan, Budi [ORNL

2012-09-01T23:59:59.000Z

89

Annual update for the Nevada Test Site site treatment plan  

SciTech Connect (OSTI)

This document describes the purpose and scope of the Draft Annual Update for the Nevada Test Site Treatment Plan, the framework for developing the Annual Update, and the current inventory of mixed waste covered under the Site Treatment Plan and the Federal Facility Compliance Act Consent Order and stored at the Nevada Test Site. No Site Treatment Plan milestones or Federal Facility Cleanup Act Consent Order deadlines have been missed for fiscal year 1996. The Shipping Cask, a portion of the solvent sludge waste stream, and eight B-25 boxes from the lead-contaminated soil waste stream have been deleted from the Site Treatment Plan and the Federal Facility Cleanup Act Consent Order, in accordance with Part XI of the Federal Facility Cleanup Act Consent Order.

NONE

1997-04-01T23:59:59.000Z

90

Integrated Waste Treatment Unit GFSI Risk Management Plan  

SciTech Connect (OSTI)

This GFSI Risk Management Plan (RMP) describes the strategy for assessing and managing project risks for the Integrated Waste Treatment Unit (IWTU) that are specifically within the control and purview of the U.S. Department of Energy (DOE), and identifies the risks that formed the basis for the DOE contingency included in the performance baseline. DOE-held contingency is required to cover cost and schedule impacts of DOE activities. Prior to approval of the performance baseline (Critical Decision-2) project cost contingency was evaluated during a joint meeting of the Contractor Management Team and the Integrated Project Team for both contractor and DOE risks to schedule and cost. At that time, the contractor cost and schedule risk value was $41.3M and the DOE cost and schedule risk contingency value is $39.0M. The contractor cost and schedule risk value of $41.3M was retained in the performance baseline as the contractor's management reserve for risk contingency. The DOE cost and schedule risk value of $39.0M has been retained in the performance baseline as the DOE Contingency. The performance baseline for the project was approved in December 2006 (Garman 2006). The project will continue to manage to the performance baseline and change control thresholds identified in PLN-1963, ''Idaho Cleanup Project Sodium-Bearing Waste Treatment Project Execution Plan'' (PEP).

W. A. Owca

2007-06-21T23:59:59.000Z

91

IFE Chamber Technology Testing Program In NIF and Chamber Development Test Plan Mohamed A. Abdou  

E-Print Network [OSTI]

. As ITER serves as a fusion testing facility for magnetic fusion energy (MFE) nuclear technology componentIFE Chamber Technology Testing Program In NIF and Chamber Development Test Plan Mohamed A. Abdou chamber technology testing program in NIF involoving: criteria for evaluation

Abdou, Mohamed

92

Integrated system dynamics toolbox for water resources planning.  

SciTech Connect (OSTI)

Public mediated resource planning is quickly becoming the norm rather than the exception. Unfortunately, supporting tools are lacking that interactively engage the public in the decision-making process and integrate over the myriad values that influence water policy. In the pages of this report we document the first steps toward developing a specialized decision framework to meet this need; specifically, a modular and generic resource-planning ''toolbox''. The technical challenge lies in the integration of the disparate systems of hydrology, ecology, climate, demographics, economics, policy and law, each of which influence the supply and demand for water. Specifically, these systems, their associated processes, and most importantly the constitutive relations that link them must be identified, abstracted, and quantified. For this reason, the toolbox forms a collection of process modules and constitutive relations that the analyst can ''swap'' in and out to model the physical and social systems unique to their problem. This toolbox with all of its modules is developed within the common computational platform of system dynamics linked to a Geographical Information System (GIS). Development of this resource-planning toolbox represents an important foundational element of the proposed interagency center for Computer Aided Dispute Resolution (CADRe). The Center's mission is to manage water conflict through the application of computer-aided collaborative decision-making methods. The Center will promote the use of decision-support technologies within collaborative stakeholder processes to help stakeholders find common ground and create mutually beneficial water management solutions. The Center will also serve to develop new methods and technologies to help federal, state and local water managers find innovative and balanced solutions to the nation's most vexing water problems. The toolbox is an important step toward achieving the technology development goals of this center.

Reno, Marissa Devan; Passell, Howard David; Malczynski, Leonard A.; Peplinski, William J.; Tidwell, Vincent Carroll; Coursey, Don (University of Chicago, Chicago, IL); Hanson, Jason (University of New Mexico, Albuquerque, NM); Grimsrud, Kristine (University of New Mexico, Albuquerque, NM); Thacher, Jennifer (University of New Mexico, Albuquerque, NM); Broadbent, Craig (University of New Mexico, Albuquerque, NM); Brookshire, David (University of New Mexico, Albuquerque, NM); Chemak, Janie (University of New Mexico, Albuquerque, NM); Cockerill, Kristan (Cockeril Consulting, Boone, NC); Aragon, Carlos (New Mexico Univeristy of Technology and Mining (NM-TECH), Socorro, NM); Hallett, Heather (New Mexico Univeristy of Technology and Mining (NM-TECH), Socorro, NM); Vivoni, Enrique (New Mexico Univeristy of Technology and Mining (NM-TECH), Socorro, NM); Roach, Jesse

2006-12-01T23:59:59.000Z

93

Building system integration research: recommendations for a US Department of Energy multiyear program plan  

SciTech Connect (OSTI)

This plan describes the scope, technical content, and resources required to conduct the Building System Integration (BSI) research program during FY 1987 through 1991. System integration research is defined, the need for the research is discussed, its benefits are outlined, and the history of building system integration research is summarized. The program scope, the general approach taken in developing this program plan, and the plan's contents are also described.

Not Available

1986-01-01T23:59:59.000Z

94

Hanford Site waste management and environmental restoration integration plan  

SciTech Connect (OSTI)

The Hanford Site Waste Management and Environmental Restoration Integration Plan'' describes major actions leading to waste disposal and site remediation. The primary purpose of this document is to provide a management tool for use by executives who need to quickly comprehend the waste management and environmental restoration programs. The Waste Management and Environmental Restoration Programs have been divided into missions. Waste Management consists of five missions: double-shell tank (DST) wastes; single-shell tank (SST) wastes (surveillance and interim storage, stabilization, and isolation); encapsulated cesium and strontium; solid wastes; and liquid effluents. Environmental Restoration consists of two missions: past practice units (PPU) (including characterization and assessment of SST wastes) and surplus facilities. For convenience, both aspects of SST wastes are discussed in one place. A general category of supporting activities is also included. 20 refs., 14 figs., 7 tabs.

Merrick, D.L.

1990-04-30T23:59:59.000Z

95

Integration of well test analysis into naturally fractured reservoir simulation  

E-Print Network [OSTI]

of the requirements for the degree of MASTER OF SCIENCE December 2005 Major Subject: Petroleum Engineering INTEGRATION OF WELL TEST ANALYSIS INTO A NATURALLY FRACTURED RESERVOIR SIMULATION A Thesis by LAURA..., W. John Lee Wayne M. Ahr Head of Department, Stephen A. Holditch December 2005 Major Subject: Petroleum Engineering iii ABSTRACT Integration of Well Test Analysis into a Naturally Fractured Reservoir...

Perez Garcia, Laura Elena

2006-04-12T23:59:59.000Z

96

Test Planning and Test Resource Optimization for Droplet-Based Microfluidic Systems*  

E-Print Network [OSTI]

Test Planning and Test Resource Optimization for Droplet-Based Microfluidic Systems* Fei Su, Sule of droplet- based microfluidic systems for safety-critical biomedical applications. In order to ensure reliability, microsystems incorporating microfluidic components must be tested adequately. In this paper, we

Chakrabarty, Krishnendu

97

Tank waste remediation system integrated technology plan. Revision 2  

SciTech Connect (OSTI)

The Hanford Site, located in southeastern Washington State, is operated by the US Department of Energy (DOE) and its contractors. Starting in 1943, Hanford supported fabrication of reactor fuel elements, operation of production reactors, processing of irradiated fuel to separate and extract plutonium and uranium, and preparation of plutonium metal. Processes used to recover plutonium and uranium from irradiated fuel and to recover radionuclides from tank waste, plus miscellaneous sources resulted in the legacy of approximately 227,000 m{sup 3} (60 million gallons) of high-level radioactive waste, currently in storage. This waste is currently stored in 177 large underground storage tanks, 28 of which have two steel walls and are called double-shell tanks (DSTs) an 149 of which are called single-shell tanks (SSTs). Much of the high-heat-emitting nuclides (strontium-90 and cesium-137) has been extracted from the tank waste, converted to solid, and placed in capsules, most of which are stored onsite in water-filled basins. DOE established the Tank Waste Remediation System (TWRS) program in 1991. The TWRS program mission is to store, treat, immobilize and dispose, or prepare for disposal, the Hanford tank waste in an environmentally sound, safe, and cost-effective manner. Technology will need to be developed or improved to meet the TWRS program mission. The Integrated Technology Plan (ITP) is the high-level consensus plan that documents all TWRS technology activities for the life of the program.

Eaton, B.; Ignatov, A.; Johnson, S.; Mann, M.; Morasch, L.; Ortiz, S.; Novak, P. [eds.] [Pacific Northwest Lab., Richland, WA (United States)

1995-02-28T23:59:59.000Z

98

DNFSB Recommendation 94-1 Hanford site integrated stabilization management plan, volumes 1 and 2  

SciTech Connect (OSTI)

This document comprises the Hanford Site Integrated Stabilization Management Plan (SISMP). This document describes the DOE`s plans at the Hanford Site to address concerns identified in Defense Nuclear Facilites Safety Board (DNFSB) Recommendation 94-1. This document also identifies plans for other spent nuclear fuel (SNF) inventories at the Hanford Site which are not within the scope of DNFSB Recommendation 94-1 for reference purposes because of their interrelationship with plans for SNF within the scope of DNFSB Recommendation 94-1. The SISMP was also developed to assist DOE in initial formulation of the Research and Development Plan and the Integrated Facilities Plan.

Gerber, E.W.

1996-03-15T23:59:59.000Z

99

Test Plan: Sludge Treatment Project Corrosion Process Chemistry Follow-on Testing  

SciTech Connect (OSTI)

This test plan was prepared by the Pacific Northwest National Laboratory (PNNL) under contract with Fluor Hanford (FH). The test plan describes the scope and conditions to be used to perform laboratory-scale testing of the Sludge Treatment Project (STP) hydrothermal treatment of K Basin sludge. The STP, managed for the U. S. Department of Energy (DOE) by FH, was created to design and operate a process to eliminate uranium metal from the sludge prior to packaging for Waste Isolation Pilot Plant (WIPP) by using high temperature liquid water to accelerate the reaction, produce uranium dioxide from the uranium metal, and safely discharge the hydrogen. The proposed testing builds on the approach and laboratory test findings for both K Basin sludge and simulated sludge garnered during prior testing from September 2006 to March 2007. The outlined testing in this plan is designed to yield further understanding of the nature of the chemical reactions, the effects of compositional and process variations and the effectiveness of various strategies to mitigate the observed high shear strength phenomenon observed during the prior testing. These tests are designed to provide process validation and refinement vs. process development and design input. The expected outcome is to establish a level of understanding of the chemistry such that successful operating strategies and parameters can be implemented within the confines of the existing STP corrosion vessel design. In July 2007, the DOE provided direction to FH regarding significant changes to the scope of the overall STP. As a result of the changes, FH directed PNNL to stop work on most of the planned activities covered in this test plan. Therefore, it is unlikely the testing described here will be performed. However, to preserve the test strategy and details developed to date, the test plan has been published.

Delegard, Calvin H.; Schmidt, Andrew J.; Poloski, Adam P.

2007-08-17T23:59:59.000Z

100

Robust Design of Reliability Test Plans Using Degradation Measures.  

SciTech Connect (OSTI)

With short production development times, there is an increased need to demonstrate product reliability relatively quickly with minimal testing. In such cases there may be few if any observed failures. Thus, it may be difficult to assess reliability using the traditional reliability test plans that measure only time (or cycles) to failure. For many components, degradation measures will contain important information about performance and reliability. These measures can be used to design a minimal test plan, in terms of number of units placed on test and duration of the test, necessary to demonstrate a reliability goal. Generally, the assumption is made that the error associated with a degradation measure follows a known distribution, usually normal, although in practice cases may arise where that assumption is not valid. In this paper, we examine such degradation measures, both simulated and real, and present non-parametric methods to demonstrate reliability and to develop reliability test plans for the future production of components with this form of degradation.

Lane, Jonathan Wesley; Lane, Jonathan Wesley; Crowder, Stephen V.; Crowder, Stephen V.

2014-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "integrated test plan" 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

Integrating Customized Test Requirements with Traditional  

E-Print Network [OSTI]

between QA and Development by Michal Blumenstyk 4. Causes of Failures in Web Applications by Solia Pertet.9) Deployment Users Test Cases Web Application Implementation (v.1.0) User Sessions Replay Tool Test Cases-WEB, July 2006 Sreedevi Sampath . University of Delaware 5/29 Program Coverage-based Test Requirement

Sampath, Sreedevi

102

Hanford Site physical separations CERCLA treatability test plan  

SciTech Connect (OSTI)

This test plan describes specifications, responsibilities, and general procedures to be followed to conduct a physical separations soil treatability test in the North Process Pond of the 300-FF-1 Operable Unit at the Hanford Site, Washington. The objective of this test is to evaluate the use of physical separation systems as a means of concentrating chemical and radioactive contaminants into fine soil fractions and thereby minimizing waste volumes. If successful the technology could be applied to clean up millions of cubic meters of contaminated soils in waste sites at Hanford and other sites. It is not the intent of this test to remove contaminated materials from the fine soils. Physical separation is a simple and comparatively low cost technology to potentially achieve a significant reduction in the volume of contaminated soils. Organic contaminants are expected to be insignificant for the 300-FF-I Operable Unit test, and further removal of metals and radioactive contaminants from the fine fraction of soils will require secondary treatment such as chemical extraction, electromagnetic separation, or other technologies. Additional investigations/testing are recommended to assess the economic and technical feasibility of applying secondary treatment technologies, but are not within the scope of this test. This plan provides guidance and specifications for the treatability test to be conducted as a service contract. More detailed instructions and procedures will be provided as part of the vendors (sellers) proposal. The procedures will be approved by Westinghouse Hanford Company (Westinghouse Hanford) and finalized by the seller prior to initiating the test.

Not Available

1992-03-01T23:59:59.000Z

103

Test plan for performance testing of the Eaton AC-3 electric vehicle  

SciTech Connect (OSTI)

An alternating current (ac) propulsion system for an electric vehicle has been developed and tested by the Eaton Corporation. The test bed vehicle is a modified 1981 Mercury Lynx. The test plan has been prepared specifically for the third modification to this test bed and identified as the Eaton AC-3. The scope of the EG and G testing at INEL to be done on the Eaton AC-3 will include coastdown and dynamometer tests but will not include environmental, on-road, or track testing. Coastdown testing will be performed in accordance with SAE J-1263 (SAE Recommended Practice for Road Load Measurement and Dynamometer Simulation Using Coastdown Techniques).

Crumley, R.L.; Heiselmann, H.W.

1985-04-01T23:59:59.000Z

104

Integrated Performance Testing Workshop, Modules 6 - 11  

SciTech Connect (OSTI)

These modules cover performance testing of: Interior Detection Systems; Access Controls; Exterior Detection Systems; Video Assessment Systems; SNM / Contraband Detection Systems; Access Delay Elements

Leach, Janice; Torres, Teresa M.

2012-10-01T23:59:59.000Z

105

Test plan : reducing soft costs of rooftop solar installations attributed to structural considerations.  

SciTech Connect (OSTI)

This test plan is a document that provides a systematic approach to the planned testing of rooftop structures to determine their actual load carrying capacity. This document identifies typical tests to be performed, the responsible parties for testing, the general feature of the tests, the testing approach, test deliverables, testing schedule, monitoring requirements, and environmental and safety compliance.

Dwyer, Stephen F.

2013-05-01T23:59:59.000Z

106

Hanford Tank Farms Waste Certification Flow Loop Test Plan  

SciTech Connect (OSTI)

A future requirement of Hanford Tank Farm operations will involve transfer of wastes from double shell tanks to the Waste Treatment Plant. As the U.S. Department of Energy contractor for Tank Farm Operations, Washington River Protection Solutions anticipates the need to certify that waste transfers comply with contractual requirements. This test plan describes the approach for evaluating several instruments that have potential to detect the onset of flow stratification and critical suspension velocity. The testing will be conducted in an existing pipe loop in Pacific Northwest National Laboratory’s facility that is being modified to accommodate the testing of instruments over a range of simulated waste properties and flow conditions. The testing phases, test matrix and types of simulants needed and the range of testing conditions required to evaluate the instruments are described

Bamberger, Judith A.; Meyer, Perry A.; Scott, Paul A.; Adkins, Harold E.; Wells, Beric E.; Blanchard, Jeremy; Denslow, Kayte M.; Greenwood, Margaret S.; Morgen, Gerald P.; Burns, Carolyn A.; Bontha, Jagannadha R.

2010-01-01T23:59:59.000Z

107

Acceptance Test Plan for the Sludge Pickup Adaptor  

SciTech Connect (OSTI)

This test plan documents the acceptance testing of the sludge pickup adapter for potential use during PSI Phases 3 and 4 fuel cleanliness inspection activities. The adaptex is attached to the strainer tip of the vacuum wand and used to suction up residual sludge captured in a sludge collection tray. The material is vacuumed into a chamber of known volume in the sludge pickup adapter. The device serves as an aid in helping to determine whether the observed quantity of sludge is within allowable limits (1.4 cm{sup 3} per fuel assembly). This functionality test involves underwater testing in the 305 Building Cold Test Facility to verify that sludge can be successfully vacuumed from a collection tray. Ancillary activities in this acceptance test include demonstration that the sludge pickup adapter CM be successfully attached to and detached from the vacuum wand underwater.

PITNER, A.L.

2000-03-29T23:59:59.000Z

108

C-018H LERF filtration test plan. Revision 1  

SciTech Connect (OSTI)

The following outlines the plan to test the polymeric backwash filtration system at the LERF. These tests will determine if the ETF filter design is adequate. If the tests show that the design is adequate, the task will be complete. If the tests show that the technology is inadequate, it may be necessary to perform further tests to qualify other candidate filtration technologies (e.g., polymeric tubular ultrafiltration, centrifugal ultrafiltration). The criteria to determine the success or failure of the backwash filter will be based on the system`s ability to remove the bacteria and inorganic contaminants from the evaporator process condensate. The tests are designed to qualify the design basis of the filtration technology that will be used in the ETF.

Moberg, T.P.; King, C.V.

1994-08-26T23:59:59.000Z

109

INEL test plan for evaluating waste assay systems  

SciTech Connect (OSTI)

A test bed is being established at the Idaho National Engineering Laboratory (INEL) Radioactive Waste Management Complex (RWMC). These tests are currently focused on mobile or portable radioassay systems. Prior to disposal of TRU waste at the Waste Isolation Pilot Plant (WIPP), radioassay measurements must meet the quality assurance objectives of the TRU Waste Characterization Quality Assurance Program Plan. This test plan provides technology holders with the opportunity to assess radioassay system performance through a three-tiered test program that consists of: (a) evaluations using non-interfering matrices, (b) surrogate drums with contents that resemble the attributes of INEL-specific waste forms, and (c) real waste tests. Qualified sources containing a known mixture and range of radionuclides will be used for the non-interfering and surrogate waste tests. The results of these tests will provide technology holders with information concerning radioassay system performance and provide the INEL with data useful for making decisions concerning alternative or improved radioassay systems that could support disposal of waste at WIPP.

Mandler, J.W.; Becker, G.K.; Harker, Y.D.; Menkhaus, D.E.; Clements, T.L. Jr.

1996-09-01T23:59:59.000Z

110

OECD 2-D Core Concrete Interaction (CCI) tests : CCI-2 test plan, Rev. 0 January 31, 2004.  

SciTech Connect (OSTI)

The Melt Attack and Coolability Experiments (MACE) program addressed the issue of the ability of water to cool and thermally stabilize a molten core-concrete interaction when the reactants are flooded from above. These tests provided data regarding the nature of corium interactions with concrete, the heat transfer rates from the melt to the overlying water pool, and the role of noncondensable gases in the mixing processes that contribute to melt quenching. As a follow-on program to MACE, The Melt Coolability and Concrete Interaction Experiments (MCCI) project is conducting reactor material experiments and associated analysis to achieve the following objectives: (1) resolve the ex-vessel debris coolability issue through a program that focuses on providing both confirmatory evidence and test data for the coolability mechanisms identified in MACE integral effects tests, and (2) address remaining uncertainties related to long-term two-dimensional molten core-concrete interactions under both wet and dry cavity conditions. Achievement of these two program objectives will demonstrate the efficacy of severe accident management guidelines for existing plants, and provide the technical basis for better containment designs for future plants. In terms of satisfying these objectives, the Management Board (MB) approved the conduct of two long-term 2-D Core-Concrete Interaction (CCI) experiments designed to provide information in several areas, including: (i) lateral vs. axial power split during dry core-concrete interaction, (ii) integral debris coolability data following late phase flooding, and (iii) data regarding the nature and extent of the cooling transient following breach of the crust formed at the melt-water interface. The first of these two tests, CCI-1, was conducted on December 19, 2003. This test investigated the interaction of a fully oxidized 400 kg PWR core melt, initially containing 8 wt % calcined siliceous concrete, with a specially designed two-dimensional siliceous concrete test section with an initial cross-sectional area of 50 cm x 50 cm. The second of these two planned tests, CCI-2, will be conducted with a nearly identical test facility and experiment boundary conditions, but with a Limestone/Common Sand (LCS) concrete test section to investigate the effect of concrete type on the two-dimensional core-concrete interaction and debris cooling behavior. The objective of this report is to provide the overall test plan for CCI-2 to enable pretest calculations to be carried out. The report begins by providing a summary description of the CCI-2 test apparatus, followed by a description of the planned test operating procedure. Overall specifications for CCI-2 are provided in Table 1-1.

Farmer, M. T.; Kilsdonk, D. J.; Lomperski, S.; Aeschlimann, R. W.; Basu, S. (Nuclear Engineering Division)

2011-05-23T23:59:59.000Z

111

Multiscale Strategic Planning Model for the Design of Integrated Ethanol and Gasoline Supply Chain  

E-Print Network [OSTI]

1 Multiscale Strategic Planning Model for the Design of Integrated Ethanol and Gasoline Supply address the design and planning of an integrated ethanol and gasoline supply chain. We assume, distribution centers where blending takes place, and the retail gas stations where different blends of gasoline

Grossmann, Ignacio E.

112

Process Planning Using An Integrated Expert System And Neural Network Approach  

E-Print Network [OSTI]

Process Planning Using An Integrated Expert System And Neural Network Approach 1 Mark Wilhelm-9209424. 2 Corresponding author. #12;Process Planning Using An Integrated Expert System And Neural Network a unique computer aided process planner for metal furniture assembly, welding and painting using a rule

Smith, Alice E.

113

Integrated Disposal Facility FY2011 Glass Testing Summary Report  

SciTech Connect (OSTI)

Pacific Northwest National Laboratory was contracted by Washington River Protection Solutions, LLC to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility (e.g., source term). Vitrifying the low-activity waste at Hanford is expected to generate over 1.6 x 10{sup 5} m{sup 3} of glass (Certa and Wells 2010). The volume of immobilized low-activity waste (ILAW) at Hanford is the largest in the DOE complex and is one of the largest inventories (approximately 8.9 x 10{sup 14} Bq total activity) of long-lived radionuclides, principally {sup 99}Tc (t{sub 1/2} = 2.1 x 10{sup 5}), planned for disposal in a low-level waste (LLW) facility. Before the ILAW can be disposed, DOE must conduct a performance assessment (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program PNNL is implementing a strategy, consisting of experimentation and modeling, in order to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. The purpose of this report is to summarize the progress made in fiscal year (FY) 2011 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of low-activity waste glasses.

Pierce, Eric M.; Bacon, Diana H.; Kerisit, Sebastien N.; Windisch, Charles F.; Cantrell, Kirk J.; Valenta, Michelle M.; Burton, Sarah D.; Westsik, Joseph H.

2011-09-29T23:59:59.000Z

114

Integrated Performance Testing for Nonproliferation Support Project  

SciTech Connect (OSTI)

The objective of this workshop is to provide participants with training in testing techniques and methodologies for assessment of the performance of: Physical Protection system elements; Material Control and Accounting (MC&A) system elements.

Johns, Russell; Bultz, Garl Alan; Byers, Kenneth R.; Yaegle, William

2013-08-20T23:59:59.000Z

115

Integral testing of relays and circuit breakers  

SciTech Connect (OSTI)

Among all equipment types considered for seismic qualification, relays have been most extensively studied through testing due to a wide variation of their designs and seismic capacities. A temporary electrical discontinuity or ``chatter`` is the common concern for relays. A chatter duration of 2 milliseconds is typically used as an acceptance criterion to determine the seismic capability of a relay. Many electrical devices, on the other hand, receiving input signals from relays can safely tolerate a chatter level much greater than 2 ms. In Phase I of a test program, Brookhaven National Laboratory performed testing of many relay models using the 2-ms chatter criterion. In Phase II of the program, the factors influencing the relay chatter criterion, and impacts of relay chatter on medium and low voltage circuit breakers and lockout relays were investigated. This paper briefly describes the Phase II tests and presents the important observations.

Bandyopadhyay, K.K.

1993-12-31T23:59:59.000Z

116

Test plan for K-Basin fuel handling tools  

SciTech Connect (OSTI)

The purpose of this document is to provide the test plan and procedures for the acceptance testing of the handling tools enveloped for the removal of an N-Reactor fuel element from its storage canister in the K-Basins storage pool and insertion into the Single fuel Element Can for subsequent shipment to a Hot Cell for examination. Examination of these N-Reactor fuel elements is part of the overall characterization effort. New hand tools were required since previous fuel movement has involved grasping the fuel in a horizontal position. The 305 Building Cold Test Facility will be used to conduct the acceptance testing of the Fuel Handling Tools. Upon completion of this acceptance testing and any subsequent training of operators, the tools will be transferred to the 105 KW Basin for installation and use.

Bridges, A.E.

1995-02-08T23:59:59.000Z

117

Integrity assessment plan for PNL 300 area radioactive hazardous waste tank system. Final report  

SciTech Connect (OSTI)

The Pacific Northwest Laboratory (PNL), operated by Battelle Memorial Institute under contract to the U.S. Department of Energy, operates tank systems for the U.S. Department of Energy, Richland Operations Office (DOE-RL), that contain dangerous waste constituents as defined by Washington State Department of Ecology (WDOE) Dangerous Waste Regulations, Washington Administrative Code (WAC) 173-303-040(18). Chapter 173-303-640(2) of the WAC requires the performance of integrity assessments for each existing tank system that treats or stores dangerous waste, except those operating under interim status with compliant secondary containment. This Integrity Assessment Plan (IAP) identifies all tasks that will be performed during the integrity assessment of the PNL-operated Radioactive Liquid Waste Systems (RLWS) associated with the 324 and 325 Buildings located in the 300 Area of the Hanford Site. It describes the inspections, tests, and analyses required to assess the integrity of the PNL RLWS (tanks, ancillary equipment, and secondary containment) and provides sufficient information for adequate budgeting and control of the assessment program. It also provides necessary information to permit the Independent, Qualified, Registered Professional Engineer (IQRPE) to approve the integrity assessment program.

NONE

1996-03-01T23:59:59.000Z

118

Integrating Customized Test Requirements with Traditional Requirements in Web Application Testing  

E-Print Network [OSTI]

Integrating Customized Test Requirements with Traditional Requirements in Web Application Testing Existing test suite reduction techniques employed for test- ing web applications have either used-based requirements in relation to test suite reduction for web applications. We investigate the use of usage

Sampath, Sreedevi

119

Long term materials test program. Preliminary operations plan  

SciTech Connect (OSTI)

The Long Term Materials Testing (LTMT) PFB facility has been designed to duplicate the design point condition of the Coal-Fired Combined Cycle (CFCC) reference commercial plant design developed by GE under contract to DOE, including bed temperature (1750/sup 0/F), pressure (10 atm), excess air (20%), and gas residence time (1.8 sec). The test rig has a one foot diameter bed and consumes about 1.6 tons/day of coal and 0.5 tons/day of dolomite sulphur sorbent. Material specimens are contained in two test sections. The low velocity test section houses 132 pin specimens 1/4 dia., sixty of which can be cooled below the gas stream temperature. The nominal exposure environment of 1650/sup 0/F, 10 atm, 27 fps should ensure representative corrosive conditions, without erosion. The control system for the LTMT facility is designed to operate the rig in such a manner that the test specimens are subjected to constant, controlled conditions representative of the actual service environment. The Preliminary Test Plan presented in Section V outlines three phases of PFB testing, plus screening tests for candidate materials. Operating costs have been updated to reflect the preliminary rig design data and current raw material quotes. The projected operating costs have been effected by raw material costs since the time of the original estimate, but the overall cost per hour of test is still very low: $122/test hour.

None

1980-03-01T23:59:59.000Z

120

Plan for decommissioning the Tokamak Fusion Test Reactor  

SciTech Connect (OSTI)

The Tokamak Fusion Test Reactor (TFTR) Project is in the planning phase of developing a decommissioning project. A Preliminary Decontamination and Decommissioning (D D) Plan has been developed which provides a framework for the baseline approach, and the cost and schedule estimates. TFTR will become activated and contaminated with tritium after completion of the deuterium-tritium (D-T) experiments. Hence some of the D D operations will require remote handling. It is expected that all of the waste generated will be low level radioactive waste (LLW). The objective of the D D Project is to make TFTR Test Cell available for use by a new fusion experiment. This paper discusses the D D objectives, the facility to be decommissioned, estimates of activation, the technical (baseline) approach, and the assumptions used to develop cost and schedule estimates.

Spampinato, P.T.; Walton, G.R. (Princeton Univ., NJ (United States). Plasma Physics Lab.); Commander, J.C. (EG and G Idaho, Inc., Idaho Falls, ID (United States))

1993-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "integrated test plan" 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

Plan for decommissioning the Tokamak Fusion Test Reactor  

SciTech Connect (OSTI)

The Tokamak Fusion Test Reactor (TFTR) Project is in the planning phase of developing a decommissioning project. A Preliminary Decontamination and Decommissioning (D&D) Plan has been developed which provides a framework for the baseline approach, and the cost and schedule estimates. TFTR will become activated and contaminated with tritium after completion of the deuterium-tritium (D-T) experiments. Hence some of the D&D operations will require remote handling. It is expected that all of the waste generated will be low level radioactive waste (LLW). The objective of the D&D Project is to make TFTR Test Cell available for use by a new fusion experiment. This paper discusses the D&D objectives, the facility to be decommissioned, estimates of activation, the technical (baseline) approach, and the assumptions used to develop cost and schedule estimates.

Spampinato, P.T.; Walton, G.R. [Princeton Univ., NJ (United States). Plasma Physics Lab.; Commander, J.C. [EG and G Idaho, Inc., Idaho Falls, ID (United States)

1993-12-31T23:59:59.000Z

122

Closure Plan for the Area 5 Radioactive Waste Management Site at the Nevada Test Site  

SciTech Connect (OSTI)

The Area 5 Radioactive Waste Management Site (RMWS) at the Nevada Test Site (NTS) is managed and operated by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This document is the first update of the preliminary closure plan for the Area 5 RWMS at the NTS that was presented in the Integrated Closure and Monitoring Plan (DOE, 2005a). The major updates to the plan include a new closure schedule, updated closure inventory, updated site and facility characterization data, the Title II engineering cover design, and the closure process for the 92-Acre Area of the RWMS. The format and content of this site-specific plan follows the Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans (DOE, 1999a). This interim closure plan meets closure and post-closure monitoring requirements of the order DOE O 435.1, manual DOE M 435.1-1, Title 40 Code of Federal Regulations (CFR) Part 191, 40 CFR 265, Nevada Administrative Code (NAC) 444.743, and Resource Conservation and Recovery Act (RCRA) requirements as incorporated into NAC 444.8632. The Area 5 RWMS accepts primarily packaged low-level waste (LLW), low-level mixed waste (LLMW), and asbestiform low-level waste (ALLW) for disposal in excavated disposal cells.

NSTec Environmental Management

2008-09-01T23:59:59.000Z

123

ROBUST SPEECH RECOGNITION BY INTEGRATING SPEECH SEPARATION AND HYPOTHESIS TESTING  

E-Print Network [OSTI]

on recognition, noisy speech is typically preprocessed by speech enhancement algorithms, such as spectral- tral subtraction for speech enhancement followed by recognition of enhanced speech [4]. The missingROBUST SPEECH RECOGNITION BY INTEGRATING SPEECH SEPARATION AND HYPOTHESIS TESTING Soundararajan

Wang, DeLiang "Leon"

124

Leveraging enterprise architecture to enable integrated test and evaluation sustainability  

E-Print Network [OSTI]

An analysis was performed to investigate how enterprise architecting methods can be applied to an integrate test and evaluation enterprise and make it a more sustainable enterprise to provide continuous value in the face ...

Sheets, Arlan C. (Arlan Christopher)

2011-01-01T23:59:59.000Z

125

Fluor Hanford, Inc. Groundwater and Technical Integration Support (Master Project) Quality Assurance Management Plan  

SciTech Connect (OSTI)

The scope of the Fluor Hanford, Inc. Groundwater and Technical Integration Support (Master Project) is to provide technical and integration support to Fluor Hanford, Inc., including operable unit investigations at 300-FF-5 and other groundwater operable units, strategic integration, technical integration and assessments, remediation decision support, and science and technology. This Quality Assurance Management Plan provides the quality assurance requirements and processes that will be followed by the Fluor Hanford, Inc. Groundwater and Technical Integration Support (Master Project).

Fix, N. J.

2008-02-20T23:59:59.000Z

126

Experimental Test Plan for Grouting H-3 Calcine  

SciTech Connect (OSTI)

Approximately 4400 cubic meters of solid high-level waste called calcine are stored at the Idaho Nuclear Technology and Engineering Center. Under the Idaho Cleanup Project, dual disposal paths are being investigated. The first path includes calcine retrieval, package "as-is", and ship to the Monitored Geological Repository (MGR). The second path involves treatment of the calcine with such methods as vitrification or grouting. This test plan outlines the hot bench scale tests to grout actual calcine and verify that the waste form properties meet the waste acceptance criteria. This is a necessary sequential step in the process of qualifying a new waste form for repository acceptance. The archive H-3 calcine samples at the Contaminated Equipment Maintenance Building attached to New Waste Calcining Facility will be used in these tests at the Remote Analytical Laboratory. The tests are scheduled for the second quarter of fiscal year 2007.

Alan K. Herbst

2006-01-01T23:59:59.000Z

127

Hanford Integrated Planning Process: 1993 Hanford Site-specific science and technology plan  

SciTech Connect (OSTI)

This document is the FY 1993 report on Hanford Site-specific science and technology (S&T) needs for cleanup of the Site as developed via the Hanford Integrated Planning Process (HIPP). It identifies cleanup problems that lack demonstrated technology solutions and technologies that require additional development. Recommendations are provided regarding allocation of funding to address Hanford`s highest-priority technology improvement needs, technology development needs, and scientific research needs, all compiled from a Sitewide perspective. In the past, the S&T agenda for Hanford Site cleanup was sometimes driven by scientists and technologists, with minimal input from the ``problem owners`` (i.e., Westinghouse Hanford Company [WHC] staff who are responsible for cleanup activities). At other times, the problem-owners made decisions to proceed with cleanup without adequate scientific and technological inputs. Under both of these scenarios, there was no significant stakeholder involvement in the decision-making process. One of the key objectives of HIPP is to develop an understanding of the integrated S&T requirements to support the cleanup mission, (a) as defined by the needs of the problem owners, the values of the stakeholders, and the technology development expertise that exists at Hanford and elsewhere. This requires a periodic, systematic assessment of these needs and values to appropriately define a comprehensive technology development program and a complementary scientific research program. Basic to our success is a methodology that is defensible from a technical perspective and acceptable to the stakeholders.

Not Available

1993-12-01T23:59:59.000Z

128

The Mixed Waste Management Facility. Design basis integrated operations plan (Title I design)  

SciTech Connect (OSTI)

The Mixed Waste Management Facility (MWMF) will be a fully integrated, pilotscale facility for the demonstration of low-level, organic-matrix mixed waste treatment technologies. It will provide the bridge from bench-scale demonstrated technologies to the deployment and operation of full-scale treatment facilities. The MWMF is a key element in reducing the risk in deployment of effective and environmentally acceptable treatment processes for organic mixed-waste streams. The MWMF will provide the engineering test data, formal evaluation, and operating experience that will be required for these demonstration systems to become accepted by EPA and deployable in waste treatment facilities. The deployment will also demonstrate how to approach the permitting process with the regulatory agencies and how to operate and maintain the processes in a safe manner. This document describes, at a high level, how the facility will be designed and operated to achieve this mission. It frequently refers the reader to additional documentation that provides more detail in specific areas. Effective evaluation of a technology consists of a variety of informal and formal demonstrations involving individual technology systems or subsystems, integrated technology system combinations, or complete integrated treatment trains. Informal demonstrations will typically be used to gather general operating information and to establish a basis for development of formal demonstration plans. Formal demonstrations consist of a specific series of tests that are used to rigorously demonstrate the operation or performance of a specific system configuration.

NONE

1994-12-01T23:59:59.000Z

129

Advanced Test Reactor Capabilities and Future Irradiation Plans  

SciTech Connect (OSTI)

The Advanced Test Reactor (ATR), located at the Idaho National Laboratory (INL), is one of the most versatile operating research reactors in the Untied States. The ATR has a long history of supporting reactor fuel and material research for the US government and other test sponsors. The INL is owned by the US Department of Energy (DOE) and currently operated by Battelle Energy Alliance (BEA). The ATR is the third generation of test reactors built at the Test Reactor Area, now named the Reactor Technology Complex (RTC), whose mission is to study the effects of intense neutron and gamma radiation on reactor materials and fuels. The current experiments in the ATR are for a variety of customers--US DOE, foreign governments and private researchers, and commercial companies that need neutrons. The ATR has several unique features that enable the reactor to perform diverse simultaneous tests for multiple test sponsors. The ATR has been operating since 1967, and is expected to continue operating for several more decades. The remainder of this paper discusses the ATR design features, testing options, previous experiment programs, future plans for the ATR capabilities and experiments, and some introduction to the INL and DOE's expectations for nuclear research in the future.

Frances M. Marshall

2006-10-01T23:59:59.000Z

130

OTEC-1 Power System Test Program: test plan for first deployment  

SciTech Connect (OSTI)

This report describes in detail all tests planned for the first eight-month deployment of OTEC-1, a test facility constructed by the US Department of Energy in order to test heat exchangers for closed-cycle power plants using ocean thermal energy. Tests to be performed during the first-deployment period are aimed primarily at determining (1) the effectiveness of countermeasures in preventing biofouling of the heat exchanters, (2) the extent of environmental impacts associated with operation of an OTEC facility, and (3) the performance of a 1-MWe, titanium shell-and-tube evaporator and condenser pair. The condenser to be tested has plain tubes, and the evaporator employs the Linde High Flux surface on the working-fluid (ammonia) side to enhance the heat-transfer rate. This plan provides a statement of the objectives and priorities of the test program, describes the test equipment, gives a detailed account of all tests to be performed and the test schedule, and discusses provisions for management of the test program.

None

1980-03-01T23:59:59.000Z

131

DNFSB recommendation 94-1 Hanford site integrated stabilization management plan - VOLUMES 1-3  

SciTech Connect (OSTI)

The US Department of Energy (DOE) has developed an Integrated Program Plan (IPP) to address concerns identified in Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-1. The IPP describes the actions that DOE plans to implement at its various sites to convert excess fissile materials to forms or conditions suitable for safe interim storage. The baseline IPP was issued as DOE's DNFSB Recommendation 94-1 Implementation Plan (IP), which was transmitted to the DNFSB on February 28, 1995. The IPP was subsequently supplemented with an Integrated Facilities Plan and a Research and Development Plan, which further develop complex-wide research and development and long-range facility requirements and plans. These additions to the baseline IPP were developed based on a systems engineering approach that integrated facilities and capabilities at the various DOE sites and focused on attaining safe interim storage with minimum safety risks and environmental impacts. Each affected DOE site has developed a Site Integrated Stabilization Management Plan (SISMP) to identify individual site plans to implement the DNFSB Recommendation 94-1 IPP. The SISMPs were developed based on the objectives, requirements, and commitments identified in the DNFSB Recommendation 94-1 IP. The SISMPs supported formulation of the initial versions of the Integrated Facilities Plan and the Research and Development Plan. The SISMPs are periodically updated to reflect improved integration between DOE sites as identified during the IPP systems engineering evaluations. This document constitutes the Hanford SISMP. This document includes the planned work scope, costs and schedules for activities at the Hanford site to implement the DNFSB Recommendation 94-1 IPP.

Gerber, E.W.

1996-09-23T23:59:59.000Z

132

Updated FY12 Ceramic Fuels Irradiation Test Plan  

SciTech Connect (OSTI)

The Fuel Cycle Research and Development program is currently devoting resources to study of numerous fuel types with the aim of furthering understanding applicable to a range of reactors and fuel cycles. In FY11, effort within the ceramic fuels campaign focused on planning and preparation for a series of rabbit irradiations to be conducted at the High Flux Isotope Reactor located at Oak Ridge National Laboratory. The emphasis of these planned tests was to study the evolution of thermal conductivity in uranium dioxide and derivative compositions as a function of damage induced by neutron damage. Current fiscal realities have resulted in a scenario where completion of the planned rabbit irradiations is unlikely. Possibilities for execution of irradiation testing within the ceramic fuels campaign in the next several years will thus likely be restricted to avenues where strong synergies exist both within and outside the Fuel Cycle Research and Development program. Opportunities to augment the interests and needs of modeling, advanced characterization, and other campaigns present the most likely avenues for further work. These possibilities will be pursued with the hope of securing future funding. Utilization of synthetic microstructures prepared to better understand the most relevant actors encountered during irradiation of ceramic fuels thus represents the ceramic fuel campaign's most efficient means to enhance understanding of fuel response to burnup. This approach offers many of the favorable attributes embraced by the Separate Effects Testing paradigm, namely production of samples suitable to study specific, isolated phenomena. The recent success of xenon-imbedded thick films is representative of this approach. In the coming years, this strategy will be expanded to address a wider range of problems in conjunction with use of national user facilities novel characterization techniques to best utilize programmatic resources to support a science-based research program.

Nelson, Andrew T. [Los Alamos National Laboratory

2012-05-24T23:59:59.000Z

133

2014-05-16 Issuance: Test Procedures for Integrated Light-Emitting...  

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

16 Issuance: Test Procedures for Integrated Light-Emitting Diode Lamps; Supplemental Notice of Proposed Rulemaking 2014-05-16 Issuance: Test Procedures for Integrated...

134

Experiments Integrate ASP-based Planning and Diagnosis with POMDPs for  

E-Print Network [OSTI]

-POMDP: Integrating Non- monotonic Logical Reasoning and Probabilistic Planning on Mobile Robots. International. Eric Hequet, Shiqi Zhang, and Sri Harsha Atluri, as well as the REU program coordinators Dr. Susan

Sridharan, Mohan

135

Integrating the principles of strategic environmental assessment into local comprehensive land use plans in California  

E-Print Network [OSTI]

The lack of early integration with the planning and decision-making process has been a major problem in environmental assessment. Traditional project-based environmental impact assessment has inadequate incentives and capacities to incorporate...

Tang, Zhenghong

2009-05-15T23:59:59.000Z

136

TEST PLAN FOR MONITORING COOLING COILS IN A LABORATORY SETTING  

SciTech Connect (OSTI)

The objective of this research project is to understand and quantify the moisture removal performance of cooling coils at part-load conditions. The project will include a comprehensive literature review, detailed measurement of cooling coil performance in a laboratory facility, monitoring cooling systems at several field test sites, and development/validation of engineering models that can be used in energy calculations and building simulations. This document contains the detailed test plan for monitoring cooling coil performance in a laboratory setting. Detailed measurements will be taken on up to 10 direct expansion (DX) and chilled water cooling coils in various configurations to understand the impact of coil geometry and operating conditions on transient moisture condensation and evaporation.

Don B. Shirey, III

2002-04-01T23:59:59.000Z

137

NOx control subsystem test plan: LEBS Phase II  

SciTech Connect (OSTI)

It is planned that NO{sub x} control subsystem testing in support of Phase II of the Low-Emissions Boiler Systems (LEBS) Project occur in ABB Power Plant Laboratories` (PPL) pilot scale Boiler Simulation Facility (BSF). This work will be performed to provide necessary design and operational information for inclusion of an optimized NO, control subsystem in the Proof-of-Concept Test Facility (POCTF) and Commercial Generating Unit (CGU) designs. The BSF is a 50 to 90x10{sup 6} BTU/hr (15 to 26 MWt) coal, oil or natural gas fired tangential furnace designed to replicate the residence time/temperature history of a utility scale tangentially fired boiler. All major aspects of a typical utility boiler are duplicated in the BSF including the lower furnace, the ash hopper, multiple burner elevations, the arch section, superheater/reheater panels, and the convective heat transfer surfaces. The furnace walls and heat transfer surfaces are cooled by a surrounding water jacket. Steam generated is vented off at atmospheric pressure so that a constant sink temperature of 100{degrees}C (212{degrees}C) is maintained. The lower furnace water walls are selectively refractory lined to maintain an appropriate furnace gas temperature history. Refractory is required because the sink temperature (100{degrees}C) is cooler than that of a typical, utility boiler, and the surface-to-volume ratio of the BSF is greater than that of a utility boiler due to scale effects. For the subject testing, the BSF will be configured as a coal fired boiler. Design and planning activities associated with the construction of the NO{sub x} control subsystem test unit will continue through June, 1995. Additionally, the schedule for specification of certain low NO{sub x} firing system components was set to allow for precursor, internal and LEBS development activities to occur and subsequently provide necessary design parameters.

NONE

1995-03-16T23:59:59.000Z

138

Should different impact assessment instruments be integrated? Evidence from English spatial planning  

SciTech Connect (OSTI)

This paper aims at providing empirical evidence to the question as to whether integration of different instruments is achieving its aim in supporting sustainable decision making, focusing on SEA inclusive sustainability appraisal (SA) and other impact assessments (IAs) currently used in English spatial planning. Usage of IAs in addition to SA is established and an analysis of the integration approach (in terms of process, output, and assessor) as well as its effectiveness is conducted. It is found that while integration enhances effectiveness to some extent, too much integration, especially in terms of the procedural element, appears to diminish the overall effectiveness of each IA in influencing decisions as they become captured by the balancing function of SA. -- Highlights: ? The usage of different impact assessments in English spatial planning is clarified. ? The relationship between integration approach and effectiveness is analyzed. ? Results suggest that integration does not necessarily lead to more sustainable decisions. ? Careful consideration is recommended upon process integration.

Tajima, Ryo, E-mail: tajima.ryo@nies.go.jp [Interdisciplinary Graduate School of Science and Engineering, Tokyo Institute of Technology, 4259-G5-9 Nagatsuta-cho, Midori-ku, Yokoyama City, Kanagawa, 226-8502 (Japan)] [Interdisciplinary Graduate School of Science and Engineering, Tokyo Institute of Technology, 4259-G5-9 Nagatsuta-cho, Midori-ku, Yokoyama City, Kanagawa, 226-8502 (Japan); Fischer, Thomas B., E-mail: fischer@liverpool.ac.uk [Department of Geography and Planning, School of Environmental Sciences, University of Liverpool, 74 Bedford Street South, Liverpool L69 7ZQ (United Kingdom)

2013-07-15T23:59:59.000Z

139

Integrated Disposal Facility FY2010 Glass Testing Summary Report  

SciTech Connect (OSTI)

Pacific Northwest National Laboratory was contracted by Washington River Protection Solutions, LLC to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility (e.g., source term). Vitrifying the low-activity waste at Hanford is expected to generate over 1.6 × 105 m3 of glass (Puigh 1999). The volume of immobilized low-activity waste (ILAW) at Hanford is the largest in the DOE complex and is one of the largest inventories (approximately 0.89 × 1018 Bq total activity) of long-lived radionuclides, principally 99Tc (t1/2 = 2.1 × 105), planned for disposal in a low-level waste (LLW) facility. Before the ILAW can be disposed, DOE must conduct a performance assessement (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program PNNL is implementing a strategy, consisting of experimentation and modeling, in order to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. The purpose of this report is to summarize the progress made in fiscal year (FY) 2010 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of low-activity waste glasses. The emphasis in FY2010 was the completing an evaluation of the most sensitive kinetic rate law parameters used to predict glass weathering, documented in Bacon and Pierce (2010), and transitioning from the use of the Subsurface Transport Over Reactive Multi-phases to Subsurface Transport Over Multiple Phases computer code for near-field calculations. The FY2010 activities also consisted of developing a Monte Carlo and Geochemical Modeling framework that links glass composition to alteration phase formation by 1) determining the structure of unreacted and reacted glasses for use as input information into Monte Carlo calculations, 2) compiling the solution data and alteration phases identified from accelerated weathering tests conducted with ILAW glass by PNNL and Viteous State Laboratory/Catholic University of America as well as other literature sources for use in geochemical modeling calculations, and 3) conducting several initial calculations on glasses that contain the four major components of ILAW-Al2O3, B2O3, Na2O, and SiO2.

Pierce, Eric M.; Bacon, Diana H.; Kerisit, Sebastien N.; Windisch, Charles F.; Cantrell, Kirk J.; Valenta, Michelle M.; Burton, Sarah D.; Serne, R Jeffrey; Mattigod, Shas V.

2010-09-30T23:59:59.000Z

140

Integration of Refinery Planning and Crude-Oil Scheduling using Lagrangian Decomposition  

E-Print Network [OSTI]

Integration of Refinery Planning and Crude-Oil Scheduling using Lagrangian Decomposition Sylvain: refinery planning and crude-oil operations scheduling. The proposed approach consists of using Lagrangian-study and a larger refinery problem show that the Lagrangian decomposition algorithm is more robust than the other

Grossmann, Ignacio E.

Note: This page contains sample records for the topic "integrated test plan" 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

Multi-Period Production Capacity Planning for Integrated Product and Production System Design*  

E-Print Network [OSTI]

Multi-Period Production Capacity Planning for Integrated Product and Production System Design* Emre.ac.uk kazu@umich.edu .Abstract ­ This paper presents a simulation-based method to aid multi-period production capacity planning by quantifying the trade-off between product quality and production cost. The product

Saitou, Kazuhiro "Kazu"

142

The CHPRC Groundwater and Technical Integration Support (Master Project) Quality Assurance Management Plan  

SciTech Connect (OSTI)

The scope of the CH2M Hill Plateau Remediation Company, LLC (CHPRC) Groundwater and Technical Integration Support (Master Project) is for Pacific Northwest National Laboratory staff to provide technical and integration support to CHPRC. This work includes conducting investigations at the 300-FF-5 Operable Unit and other groundwater operable units, and providing strategic integration, technical integration and assessments, remediation decision support, and science and technology. The projects under this Master Project will be defined and included within the Master Project throughout the fiscal year, and will be incorporated into the Master Project Plan. This Quality Assurance Management Plan provides the quality assurance requirements and processes that will be followed by the CHPRC Groundwater and Technical Integration Support (Master Project) and all releases associated with the CHPRC Soil and Groundwater Remediation Project. The plan is designed to be used exclusively by project staff.

Fix, N. J.

2009-04-03T23:59:59.000Z

143

Abbreviated sampling and analysis plan for planning decontamination and decommissioning at Test Reactor Area (TRA) facilities  

SciTech Connect (OSTI)

The objective is to sample and analyze for the presence of gamma emitting isotopes and hazardous constituents within certain areas of the Test Reactor Area (TRA), prior to D and D activities. The TRA is composed of three major reactor facilities and three smaller reactors built in support of programs studying the performance of reactor materials and components under high neutron flux conditions. The Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR) facilities are currently pending D/D. Work consists of pre-D and D sampling of designated TRA (primarily ETR) process areas. This report addresses only a limited subset of the samples which will eventually be required to characterize MTR and ETR and plan their D and D. Sampling which is addressed in this document is intended to support planned D and D work which is funded at the present time. Biased samples, based on process knowledge and plant configuration, are to be performed. The multiple process areas which may be potentially sampled will be initially characterized by obtaining data for upstream source areas which, based on facility configuration, would affect downstream and as yet unsampled, process areas. Sampling and analysis will be conducted to determine the level of gamma emitting isotopes and hazardous constituents present in designated areas within buildings TRA-612, 642, 643, 644, 645, 647, 648, 663; and in the soils surrounding Facility TRA-611. These data will be used to plan the D and D and help determine disposition of material by D and D personnel. Both MTR and ETR facilities will eventually be decommissioned by total dismantlement so that the area can be restored to its original condition.

NONE

1994-10-01T23:59:59.000Z

144

Moving Bed, Granular Bed Filter Development Program: Option 1, Component Test Facility. Task 3, Test plan  

SciTech Connect (OSTI)

In the base contract, Combustion Power Co. developed commercial designs for a moving granular-bed filter (GBF). The proposed filter is similar to previous designs in terms of its shape and method of filtration. The commercial designs have scaled the filter from a 5 ft diameter to as large as a 20 ft diameter filter. In Task 2 of the Moving Bed-Granular Filter Development Program, all technical concerns related to the further development of the filter are identified. These issues are discussed in a Topical Report which has been issued as part of Task 2. Nineteen issues are identified in this report. Along with a discussion of these issues are the planned approaches for resolving each of these issues. These issues will be resolved in either a cold flow component test facility or in pilot scale testing at DOE`s Power System Development Facility (PSDF) located at Southem Company Services` Wilsonville facility. Task 3 presents a test plan for resolving those issues which can be addressed in component test facilities. The issues identified in Task 2 which will be addressed in the component test facilities are: GBF scale-up; effect of filter cone angle and sidewall materials on medium flow and ash segregation; maximum gas filtration rate; lift pipe wear; GBF media issues; mechanical design of the gas inlet duct; and filter pressure drop. This document describes a test program to address these issues, with testing to be performed at Combustion Power Company`s facility in Belmont, California.

Haas, J.C.; Purdhomme, J.W.; Wilson, K.B.

1994-04-01T23:59:59.000Z

145

Testing for market integration crude oil, coal, and natural gas  

SciTech Connect (OSTI)

Prompted by the contemporaneous spike in coal, oil, and natural gas prices, this paper evaluates the degree of market integration both within and between crude oil, coal, and natural gas markets. Our approach yields parameters that can be readily tested against a priori conjectures. Using daily price data for five very different crude oils, we conclude that the world oil market is a single, highly integrated economic market. On the other hand, coal prices at five trading locations across the United States are cointegrated, but the degree of market integration is much weaker, particularly between Western and Eastern coals. Finally, we show that crude oil, coal, and natural gas markets are only very weakly integrated. Our results indicate that there is not a primary energy market. Despite current price peaks, it is not useful to think of a primary energy market, except in a very long run context.

Bachmeier, L.J.; Griffin, J.M. [Texas A& amp; M Univ, College Station, TX (United States)

2006-07-01T23:59:59.000Z

146

DNFSB Recommendation 94-1 Hanford Site Integrated Stabilization Management Plan. Volume 1  

SciTech Connect (OSTI)

The US Department of Energy (DOE) has developed an Integrated Program Plan (IPP) to address concerns identified in Defense Nuclear Facilities Safety Board Recommendation 94-1. The IPP describes the actions that DOE plans to implement at its various sites to convert excess fissile materials to forms or conditions suitable for safe interim storage. The baseline IPP was issued as DOE`s Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-1 Implementation Plan (IP), which was transmitted to the DNFSB on February 28, 1995. The IPP is being further developed to include complex-wide requirements for research and development and a long-range facility requirements section. The planned additions to the baseline IPP are being developed based on a systems engineering approach that integrates facilities and capabilities at the various DOE sites and focuses on attaining safe interim storage with minimum safety risks and environmental impacts. Each affected DOE site has developed a Site Integrated Stabilization Management Plan (SISMP) to identify individual site plans to implement the DNFSB Recommendation 94-1 and to provide a basis for formulating planned additions to the IPP. The SISMPs were developed based on the objectives, requirements, and commitments identified in the baseline DNFSB Recommendation 94-1 IPP. The SISMPs will be periodically updated to reflect improved integration between DOE sites as identified during the IPP systems engineering evaluations.

Gerber, E.W.

1995-10-01T23:59:59.000Z

147

Test plan: Hydraulic fracturing and hydrologic tests in Marker Beds 139 and 140  

SciTech Connect (OSTI)

Combined hydraulic fracturing and hydrological measurements in this test plan are designed to evaluate the potential influence of fracture formation in anhydrite Marker Beds 139 and 140 on gas pressure in and gas flow from the disposal rooms in the Waste Isolation Pilot Plant with time. The tests have the further purpose of providing comparisons of permeabilities of anhydrite interbeds in an undisturbed (virgin) state and after fracture development and/or opening and dilation of preexisting partially healed fractures. Three sets of combined hydraulic fracturing and hydrological measurements are planned. A set of trial measurements is expected to last four to six weeks. The duration of each subsequent experiment is anticipated to be six to eight weeks.

Wawersik, W.R.; Beauheim, R.L.

1991-03-01T23:59:59.000Z

148

Project W-314 Specific Test and Evaluation Plan 241-AN-A Valve Pit  

SciTech Connect (OSTI)

The purpose of this Specific Test and Evaluation Plan (STEP) is to provide a detailed written plan for the systematic testing of modifications made to the 241-AN-A Valve Pit by the W-314 Project. The STEP develops the outline for test procedures that verify the system's performance to the established Project design criteria. The STEP is a lower tier document based on the W-314 Test and Evaluation Plan (TEP).

HAMMERS, J.S.

1999-08-25T23:59:59.000Z

149

A Tool for Integrated Planning of Water Infrastructure Gwendolyn Woods  

E-Print Network [OSTI]

or inaccurate. Economy of scale for wastewater reclamation (treatment) facilities may conflict with the energy. Yet the need to plan for new water and wastewater infrastructure remains. In the Assessment of Climate Change in the Southwest United States: A Report Prepared for the National Climate Assessment, Theobald et

Fay, Noah

150

Well test plan for the City of El Centro utility core field experiment  

SciTech Connect (OSTI)

The following are included in the well test plan: well test program schedule and order of work; the injection well drilling program details; the production well drilling program details; and long-term (30-day) production testing program details. (MHR)

Not Available

1981-06-15T23:59:59.000Z

151

Apparatus and method for defect testing of integrated circuits  

DOE Patents [OSTI]

An apparatus and method for defect and failure-mechanism testing of integrated circuits (ICs) is disclosed. The apparatus provides an operating voltage, V.sub.DD, to an IC under test and measures a transient voltage component, V.sub.DDT, signal that is produced in response to switching transients that occur as test vectors are provided as inputs to the IC. The amplitude or time delay of the V.sub.DDT signal can be used to distinguish between defective and defect-free (i.e. known good) ICs. The V.sub.DDT signal is measured with a transient digitizer, a digital oscilloscope, or with an IC tester that is also used to input the test vectors to the IC. The present invention has applications for IC process development, for the testing of ICs during manufacture, and for qualifying ICs for reliability.

Cole, Jr., Edward I. (Albuquerque, NM); Soden, Jerry M. (Placitas, NM)

2000-01-01T23:59:59.000Z

152

Apparatus and method for defect testing of integrated circuits  

SciTech Connect (OSTI)

An apparatus and method for defect and failure-mechanism testing of integrated circuits (ICs) is disclosed. The apparatus provides an operating voltage, V(DD), to an IC under test and measures a transient voltage component, V(DDT), signal that is produced in response to switching transients that occur as test vectors are provided as inputs to the IC. The amplitude or time delay of the V(DDT) signal can be used to distinguish between defective and defect-free (i.e. known good) ICs. The V(DDT) signal is measured with a transient digitizer, a digital oscilloscope, or with an IC tester that is also used to input the test vectors to the IC. The present invention has applications for IC process development, for the testing of ICs during manufacture, and for qualifying ICs for reliability.

Cole, E.I. Jr.; Soden, J.M.

2000-02-29T23:59:59.000Z

153

U.S. Plans and Strategy for ITER Blanket Testing  

SciTech Connect (OSTI)

Testing blanket concepts in the integrated fusion environment is one of the principal objectives of ITER. Blanket test modules will be inserted in ITER from Day 1 of its operation and will provide the first experimental data on the feasibility of the D-T cycle for fusion. With the US rejoining ITER, the US community has decided to have strong participation in the ITER Test Blanket Module (TBM) Program. A US strategy for ITER-TBM has evolved that emphasizes international collaboration. A study was initiated to select the two blanket options for the US ITER-TBM in light of new R and D results from the US and world programs over the past decade. The study is led by the Plasma Chamber community in partnership with the Materials, PFC, Safety, and physics communities. The study focuses on assessment of the critical feasibility issues for candidate blanket concepts and it is strongly coupled to R and D of modeling and experiments. Examples of issues are MHD insulators, SiC insert viability and compatibility with PbLi, tritium permeation, MHD effects on heat transfer, solid breeder 'temperature window' and thermomechanics, and chemistry control of molten salts. A dual coolant liquid breeder and a helium-cooled solid breeder blanket concept have been selected for the US ITER-TBM.

Abdou, M. [UCLA Fusion Engineering Sciences (United States); Sze, D. [UCSD Advanced Energy Technology Group (United States); Wong, C. [General Atomics (United States); Sawan, M. [University of Wisconsin Fusion Technology Institute, Madison (United States); Ying, A. [UCLA Fusion Engineering Sciences (United States); Morley, N.B. [UCLA Fusion Engineering Sciences (United States); Malang, S

2005-04-15T23:59:59.000Z

154

Biointrusion test plan for the Permanent Isolation Surface Barrier Prototype  

SciTech Connect (OSTI)

This document provides a testing and monitoring plan for the biological component of the prototype barrier slated for construction at the Hanford Site. The prototype barrier is an aboveground structure engineered to demonstrate the basic features of an earthen cover system. It is designed to permanently isolate waste from the biosphere. The features of the barrier include multiple layers of soil and rock materials and a low-permeability asphalt sublayer. The surface of the barrier consists of silt loam soil, covered with plants. The barrier sides are reinforced with rock or coarse earthen-fill to protect against wind and water erosion. The sublayers inhibit plant and animal intrusion and percolation of water. A series of tests will be conducted on the prototype barrier over the next several years to evaluate barrier performance under extreme climatic conditions. Plants and animals will play a significant role in the hydrologic and water and wind erosion characteristics of the prototype barrier. Studies on the biological component of the prototype barrier will include work on the initial revegetation of the surface, continued monitoring of the developing plant community, rooting depth and dispersion in the context of biointrusion potential, the role of plants in the hydrology of the surface and toe regions of the barrier, the role of plants in stabilizing the surface against water and wind erosion, and the role of burrowing animals in the hydrology and water and wind erosion of the barrier.

Link, S.O.; Cadwell, L.L.; Brandt, C.A.; Downs, J.L.; Rossi, R.E.; Gee, G.W.

1994-04-01T23:59:59.000Z

155

ART CCIM Phase II-A Off-Gas System Evaluation Test Plan  

SciTech Connect (OSTI)

This test plan defines testing to be performed using the Idaho National Laboratory (INL) engineering-scale cold crucible induction melter (CCIM) test system for Phase II-A of the Advanced Remediation Technologies (ART) CCIM Project. The multi-phase ART-CCIM Project is developing a conceptual design for replacing the joule-heated melter (JHM) used to treat high level waste (HLW) in the Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS) with a cold crucible induction melter. The INL CCIM test system includes all feed, melter off-gas control, and process control subsystems needed for fully integrated operation and testing. Testing will include operation of the melter system while feeding a non-radioactive slurry mixture prepared to simulate the same type of waste feed presently being processed in the DWPF. Process monitoring and sample collection and analysis will be used to characterize the off-gas composition and properties, and to show the fate of feed constituents, to provide data that shows how the CCIM retrofit conceptual design can operate with the existing DWPF off-gas control system.

Nick Soelberg; Jay Roach

2009-01-01T23:59:59.000Z

156

Interim Test Procedures for Evaluating Electrical Performance and Grid Integration of Vehicle-to-Grid Applications  

SciTech Connect (OSTI)

The objective of this report is to provide a test plan for V2G testing. The test plan is designed to test and evaluate the vehicle's power electronics capability to provide power to the grid, and to evaluate the vehicle's ability to connect and disconnect from the utility according to a subset of the IEEE Std. 1547 tests.

Chakraborty, S.; Kramer, W.; Kroposki, B.; Martin, G.; McNutt, P.; Kuss, M.; Markel, T.; Hoke, A.

2011-06-01T23:59:59.000Z

157

DNFSB recommendation 94-1 Hanford site integrated stabilization management plan  

SciTech Connect (OSTI)

In May 1994, the Defense Nuclear Facilities Safety Board (DNFSB) issued DNFSB Recommendation 94-1 (Conway 1994), which identified concerns related to US Department of Energy (DOE) management of legacy fissile materials remaining from past defense production activities. The DNFSB expressed concern about the existing storage conditions for these materials and the slow pace at which the conditions were being remediated. The DNFSB also expressed its belief that additional delays in stabilizing these fissile materials would be accompanied by further deterioration of safety and unnecessary increased risks to workers and the public. In February 1995, DOE issued the DNFSB Recommendation 94-1 Implementation Plan (O`Leary 1995) to address the concerns identified in DNFSB Recommendation 94-1. The Implementation Plan (IP) identifies several DOE commitments to achieve safe interim storage for the legacy fissile materials, and constitutes DOE`s baseline DNFSB Recommendation 94-1 Integrated Program Plan (IPP). The IPP describes the actions DOE plans to implement within the DOE complex to convert its excess fissile materials to forms or conditions suitable for safe interim storage. The IPP was subsequently supplemented with an Integrated Facilities Plan and a Research and Development Plan, which further develop complex-wide research and development and long-range facility requirements and plans. The additions to the baseline IPP were developed based on a systems engineering approach that integrated facilities and capabilities at the various DOE sites and focused on attaining safe interim storage with minimum safety risks and environmental impacts. Each affected DOE site has developed a Site Integrated Stabilization Management Plan (SISMP) to identify individual site plans to implement the DNFSB Recommendation 94-1 IPP. The SISMPs were developed based on the objectives, requirements, and commitments identified in the DNFSB Recommendation 94-1 IP. The SISMPs also supported formulation of the initial versions of the Integrated Facilities Plan and the Research and Development Plan. The SISMPs are periodically updated to reflect improved integration between DOE sites as identified during the IPP systems engineering evaluations. This document is the fifth update of the Hanford SISMP.

McCormack, R.L.

1997-05-07T23:59:59.000Z

158

Method of and apparatus for testing the integrity of filters  

DOE Patents [OSTI]

A method of and apparatus are disclosed for testing the integrity of individual filters or filter stages of a multistage filtering system including a diffuser permanently mounted upstream and/or downstream of the filter stage to be tested for generating pressure differentials to create sufficient turbulence for uniformly dispersing trace agent particles within the airstream upstream and downstream of such filter stage. Samples of the particle concentration are taken upstream and downstream of the filter stage for comparison to determine the extent of particle leakage past the filter stage. 5 figs.

Herman, R.L.

1985-05-07T23:59:59.000Z

159

Microsoft Word - 911144_0_SSC-13 S-I HPS Test Plan_rel.doc  

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

4 Revision 0 ENGINEERING SERVICES FOR THE NEXT GENERATION NUCLEAR PLANT (NGNP) WITH HYDROGEN PRODUCTION Test Plan for S-I Hydrogen Production System (HPS) Prepared by General...

160

Microsoft Word - 911136_0 SSC-4b Reactor Graphite Test Plan_rel...  

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

6 Revision 0 Engineering Services for the Next Generation Nuclear Plant (NGNP) with Hydrogen Production Test Plan for Reactor Graphite Elements Prepared by General Atomics for the...

Note: This page contains sample records for the topic "integrated test plan" 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

Microsoft Word - 911141_0_SSC-9 RCCS Test Plan.doc  

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

1 Revision 0 ENGINEERING SERVICES FOR THE NEXT GENERATION NUCLEAR PLANT (NGNP) WITH HYDROGEN PRODUCTION Test Plan for the Reactor Cavity Cooling System Prepared by General Atomics...

162

Microsoft Word - 911145_0_SSC-14 FHSS Test Plan_rel.doc  

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

5 Revision 0 ENGINEERING SERVICES FOR THE NEXT GENERATION NUCLEAR PLANT (NGNP) WITH HYDROGEN PRODUCTION Test Plan - Fuel Handling and Storage System Prepared by General Atomics For...

163

Microsoft Word - 911138_0_SSC-6 Helium Circulator Test Plan_rel...  

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

8 Revision 0 ENGINEERING SERVICES FOR THE NEXT GENERATION NUCLEAR PLANT (NGNP) WITH HYDROGEN PRODUCTION Test Plan for Helium Circulators (PHTS, SCS, SHTS) Prepared by General...

164

Microsoft Word - 911135_0 SSC-4a Reactor Core Test Plan_rel.doc  

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

5 Revision 0 ENGINEERING SERVICES FOR THE NEXT GENERATION NUCLEAR PLANT (NGNP) WITH HYDROGEN PRODUCTION Test Plan for the Reactor Core Assembly Prepared by General Atomics For the...

165

Microsoft Word - 911140_0_SCHE Test Plan_rel.doc  

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

0 Revision 0 ENGINEERING SERVICES FOR THE NEXT GENERATION NUCLEAR PLANT (NGNP) WITH HYDROGEN PRODUCTION Test Plan - Shutdown Cooling Heat Exchanger Prepared by General Atomics For...

166

Microsoft Word - 911133_0 SSC-1 Test Plan_rel.doc  

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

3 Revision 0 ENGINEERING SERVICES FOR THE NEXT GENERATION NUCLEAR PLANT (NGNP) WITH HYDROGEN PRODUCTION Test Plan for Reactor Control Equipment Prepared by General Atomics For the...

167

Microsoft Word - 911139_0_SSC-7 IHX Test Plan_rel.doc  

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

9 Revision 0 ENGINEERING SERVICES FOR THE NEXT GENERATION NUCLEAR PLANT (NGNP) WITH HYDROGEN PRODUCTION Test Plan - Intermediate Heat Exchanger PCHE Type Prepared by General...

168

Microsoft Word - 911134_0 SSC-2 Control Rod Test Plan_rel.doc  

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

4 Revision 0 ENGINEERING SERVICES FOR THE NEXT GENERATION NUCLEAR PLANT (NGNP) WITH HYDROGEN PRODUCTION Test Plan - Control Rods Prepared by General Atomics For the Battelle Energy...

169

Microsoft Word - 911143_0_SSC-11 PCS Test Plan_rel.doc  

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

3 Revision 0 ENGINEERING SERVICES FOR THE NEXT GENERATION NUCLEAR PLANT (NGNP) WITH HYDROGEN PRODUCTION Test Plan - Power Conversion System Equipment for a Direct Combined Cycle...

170

Microsoft Word - 911137_0 SSC-5 RPV Test Plan_rel.doc  

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

7 Revision 0 ENGINEERING SERVICES FOR THE NEXT GENERATION NUCLEAR PLANT (NGNP) WITH HYDROGEN PRODUCTION Test Plan - Reactor Pressure Vessel Prepared by General Atomics For the...

171

Microsoft Word - 911147_0_SSC-16 RPS IPS and PCDIS Test Plan...  

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

7 Revision 0 ENGINEERING SERVICES FOR THE NEXT GENERATION NUCLEAR PLANT (NGNP) WITH HYDROGEN PRODUCTION Test Plan for RPS, IPS and PCDIS Prepared by General Atomics For the...

172

DNFSB Recommendation 94-1 Hanford Site Integrated Stabilization Management Plan. Volume 2  

SciTech Connect (OSTI)

The Hanford Site Integrated Stabilization Management Plan (SISMP) was developed in support of the US Department of Energy`s (DOE) Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-1 Integrated Program Plan (IPP). Volume 1 of the SISMP identifies the technical scope and costs associated with Hanford Site plans to resolve concerns identified in DNFSB Recommendation 94-1. Volume 2 of the SISMP provides the Resource Loaded Integrated Schedules for Spent Nuclear Fuel Project and Plutonium Finishing Plant activities identified in Volume 1 of the SISMP. Appendix A provides the schedules and progress curves related to spent nuclear fuel management. Appendix B provides the schedules and progress curves related to plutonium-bearing material management. Appendix C provides programmatic logic diagrams that were referenced in Volume 1 of the SISMP.

Gerber, E.W.

1995-10-01T23:59:59.000Z

173

The integrated tank waste management plan at Oak Ridge National Laboratory  

SciTech Connect (OSTI)

DOE`s Environmental Management Program at Oak Ridge has developed an integrated tank waste management plan that combines the accelerated deployment of innovative technologies with an aggressive waste transfer schedule. Oak Ridge is cleaning out waste from aging underground storage tanks in preparation of waste processing, packaging and final safe disposal. During remediation this plan will reduce the risk of environmental, worker, and civilian exposure, save millions of dollars, and cut years off of tank remediation schedules at Oak Ridge.

Billingsley, K. [STEP, Inc., Oak Ridge, TN (United States); Mims, C. [Dept. of Energy, Oak Ridge, TN (United States). Oak Ridge Operations Office; Robinson, S. [Oak Ridge National Lab., TN (United States)

1998-06-01T23:59:59.000Z

174

Integrated Safety Management System as the Basis for Work Planning and Control for Research and Development  

Broader source: Energy.gov [DOE]

Slide Presentation by Rich Davies, Kami Lowry, Mike Schlender, Pacific Northwest National Laboratory (PNNL) and Ted Pietrok, Pacific Northwest Site Office (PNSO). Integrated Safety Management System as the Basis for Work Planning and Control for Research and Development. Work Planning and Control (WP&C) is essential to assuring the safety of workers and the public regardless of the scope of work Research and Development (R&D) activities are no exception.

175

Site planning and integration fiscal year 1999 multi-year work plan (MYWP) update for WBS 1.8.2.1  

SciTech Connect (OSTI)

The primary mission of the Site Planning and Integration (SP and I) project is to assist Fluor Daniel Project Direction to ensure that all work performed under the Project Hanford Management Contract (PHMC) is adequately planned, executed, controlled, and that performance is measured and reported in an integrated fashion. Furthermore, SP and I is responsible for the development, implementation, and management of systems and processes that integrate technical, schedule, and cost baselines for PHMC work.

SCHULTZ, E.A.

1998-10-01T23:59:59.000Z

176

Improving DOE Project Performance Using the DOD Integrated Master Plan - 12481  

SciTech Connect (OSTI)

DOE O 413 measures a project's progress to plan by the consumption of funding, the passage of time, and the meeting of milestones. In March of 2003, then Under Secretary, Energy, Science, Card received a memo directing the implementation of Project Management and the Project Management Manual, including the Integrated Master Plan and Integrated Master Schedule. This directive states 'the integrated master plan and schedule tie together all project tasks by showing their logical relationships and any constraints controlling the start or finish of each task. This process results in a hierarchy of related functional and layered schedules derived from the Work Breakdown Structure that can be used for monitoring and controlling project progress'. This paper shows how restoring the IMP/IMS paradigm to DOE program management increases the probability of program success in ways not currently available using DOD O 413 processes alone. Using DOE O 413 series guidance, adding the Integrated Master Plan and Integrated Master Schedule paradigm would provide a hierarchical set of performance measures for each 'package of work,' that provides measurable visibility to the increasing maturity of the project. This measurable maturity provides the mechanism to forecast future performance of cost, schedule, and technical outcomes in ways not available using just the activities in DOE O 413. With this information project managers have another tool available to address the issues identified in GAO-07-336 and GAO-09-406. (authors)

Alleman, Glen B. [DOD Programs, Project Time and Cost (United States); Nosbisch, Michael R. [Managing Principle, Western Region, Project Time and Cost (United States)

2012-07-01T23:59:59.000Z

177

Resource Planning Model: An Integrated Resource Planning and Dispatch Tool for Regional Electric Systems  

SciTech Connect (OSTI)

This report introduces a new capacity expansion model, the Resource Planning Model (RPM), with high spatial and temporal resolution that can be used for mid- and long-term scenario planning of regional power systems. Although RPM can be adapted to any geographic region, the report describes an initial version of the model adapted for the power system in Colorado. It presents examples of scenario results from the first version of the model, including an example of a 30%-by-2020 renewable electricity penetration scenario.

Mai, T.; Drury, E.; Eurek, K.; Bodington, N.; Lopez, A.; Perry, A.

2013-01-01T23:59:59.000Z

178

Improving the effectiveness of planning EIA (PEIA) in China: Integrating planning and assessment during the preparation of Shenzhen's Master Urban Plan  

SciTech Connect (OSTI)

The enactment and implementation of the 2003 EIA Law in China institutionalised the role of plan environmental impact assessment (PEIA). While the philosophy, methodology and mechanisms of PEIA have gradually permeated through the various levels of government with a positive effect on the process and outcome of urban planning, only a few cities in China have so far carried out PEIA as a Strategic Environmental Assessment (SEA)-type procedure. One such case is the southern city of Shenzhen. During the past three decades, Shenzhen has grown from a small town to a large and booming city as China has successfully and rapidly developed its economy by adopting the 'reform and open door' policy. In response to the challenges arising from the generally divergent processes of rapid urbanisation, economic transformation and environment protection, Shenzhen has incrementally adopted the SEA concept in developing the city's Master Urban Plan. As such, this paper reviews the effectiveness of PEIA in three ways: {center_dot}as a tool and process for achieving more sustainable and strategic planning; {center_dot}to determine the level of integration of SEA within the planning system; and, {center_dot}its effectiveness vis-a-vis implementation. The implementation of PEIA within Shenzhen's Master Urban Plan offers important insights into the emergence of innovative practices in undertaking PEIA as well as theoretical contributions to the field, especially in exploring the relationship between PEIA and SEA and highlighting the central role of local governing institutions in SEA development.

Che Xiuzhen, E-mail: chexiuzhen@sohu.com [Shenzhen Academy of Environmental Science, Shenzhen, Guangdong (China); English, Alex [Centre for Strategic Economic Studies, Victoria University (Australia); Lu Jia [Shenzhen Urban Planning and Research Center, Shenzhen, Guangdong (China); Chen, Yongqin David [Department of Geography and Resource Management, Chinese University of Hong Kong, Hong Kong (Hong Kong); Centre of Strategic Environmental Assessment for China, Chinese University of Hong Kong, Hong Kong (Hong Kong)

2011-11-15T23:59:59.000Z

179

Fire Alarm Testing and Inspection Planning and Vendor Check In/Check Out Process  

E-Print Network [OSTI]

Fire Alarm Testing and Inspection Planning and Vendor Check In/Check Out Process DOCUMENT PURPOSE This process is used for fire alarm testing and inspection pre-work planning and vendor check in and check out. BUILDING NAME/#: ___________________/_____ VENDOR: ________________________ TECHNICIAN

Webb, Peter

180

Relay test program. Series 2 tests: Integral testing of relays and circuit breakers  

SciTech Connect (OSTI)

This report presents the results of a relay test program conducted by Brookhaven National Laboratory (BNL) under the sponsorship of the US Nuclear Regulatory Commission (NRC). The program is a continuation of an earlier test program the results of which were published in NUREG/CR-4867. The current program was carried out in two phases: electrical testing and vibration testing. The objective was primarily to focus on the electrical discontinuity or continuity of relays and circuit breaker tripping mechanisms subjected to electrical pulses and vibration loads. The electrical testing was conducted by KEMA-Powertest Company and the vibration testing was performed at Wyle Laboratories, Huntsville, Alabama. This report discusses the test procedures, presents the test data, includes an analysis of the data and provides recommendations regarding reliable relay testing.

Bandyopadhyay, K.K.; Kunkel, C.; Shteyngart, S. [Brookhaven National Lab., Upton, NY (United States)

1994-02-01T23:59:59.000Z

Note: This page contains sample records for the topic "integrated test plan" 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

Integration plan required by performance agreement SM 7.2.1  

SciTech Connect (OSTI)

Fluor Daniel Hanford, Inc. and its major subcontractors are in agreement that environmental monitoring performed under the Project Hanford Management Contract is to be done in accordance with a single, integrated program. The purpose of this Integration Plan for Environmental Monitoring is to document the policies, systems, and processes being put in place to meet one key objective: manage and integrate a technically competent, multi-media ambient environmental monitoring program, in an efficient, cost effective manner. Fluor Daniel Hanford, Inc. and its major subcontractors also commit to conducting business in a manner consistent with the International Standards Organization 14000 Environmental Management System concepts. Because the integration of sitewide groundwater monitoring activities is managed by the Environmental Restoration Contractor, groundwater monitoring it is outside the scope of this document. Therefore, for the purpose of this Integration Plan for Environmental Monitoring, the Integrated Environmental Monitoring Program is defined as applicable to all environmental media except groundwater. This document provides recommendations on future activities to better integrate the overall environmental monitoring program, with emphasis on the near-field program. In addition, included is the Fluor Daniel Hanford, Inc. team review of the environmental monitoring activities on the Hanford Site, with concurrence of Pacific Northwest National Laboratory and Bechtel Hanford, Inc. (The narrative provided later in the Discussion Section describes the review and consideration given to each topic.) This document was developed to meet the requirements of the Project Hanford Management Contract performance agreement (SM7.2) and the tenets of the U.S. Department of Energy's Effluent and Environmental Monitoring Planning Process. This Plan is prepared for the U.S. Department of Energy, Richland Operations Office, Environmental Assurance, Permits, and Policy Division to complete the requirements specified in the Performance Expectation 7.2.1, within the SM7 Environmental, Safety, and Health section of the Project Hanford Management Contract.

Diediker, L.P.

1997-03-28T23:59:59.000Z

182

STREAMLINED APPROACH FOR ENVIRONMENTAL RESTORATION PLAN FOR CORRECTIVE ACTION UNIT 116: AREA 25 TEST CELL C FACILITYNEVADA TEST SITE, NEVADA  

SciTech Connect (OSTI)

This Streamlined Approach for Environmental Restoration Plan identifies the activities required for the closure of Corrective Action Unit 116, Area 25 Test Cell C Facility. The Test Cell C Facility is located in Area 25 of the Nevada Test Site approximately 25 miles northwest of Mercury, Nevada.

NONE

2006-07-01T23:59:59.000Z

183

304 IEEE TRANSACTIONS ON RELIABILITY, VOL. 54, NO. 2, JUNE 2005 Integrating Preventive Maintenance Planning and  

E-Print Network [OSTI]

304 IEEE TRANSACTIONS ON RELIABILITY, VOL. 54, NO. 2, JUNE 2005 Integrating Preventive Maintenance & Conclusions--Preventive maintenance planning, and production scheduling are two activities that are inter-depen- dent but most often performed independently. Considering that preventive maintenance, and repair affect

Kutanoglu, Erhan

184

HSS Finding D3 Corrective Action Plan for LBNL Integrated ES&H Management Inspection  

E-Print Network [OSTI]

LNBL CAP HSS Finding D3 Corrective Action Plan for LBNL Integrated ES&H Management Inspection Owner: Ross Fisher Analyst: Weyland Wong Finding Statement D3: LBNL has not established sufficient processes for Correcting Finding: Richard DeBusk LBNL EH&S Division Laboratory Safety Manager (510) 495-2976 REDe

Knowles, David William

185

Corrective Action Plan-Special DSC Meeting LBNL Integrated ES&H Management Inspection 2009  

E-Print Network [OSTI]

Corrective Action Plan-Special DSC Meeting LBNL Integrated ES&H Management Inspection 2009 Presented April 24, 2009 Finding Statement C-4: LBNL has not established effective processes and rigorous documents that consistently and effectively communicate safety expectations and requirements to LBNL

Knowles, David William

186

A long-term investment planning model for mixed energy infrastructure integrated with renewable  

E-Print Network [OSTI]

A long-term investment planning model for mixed energy infrastructure integrated with renewable energy Jinxu Ding and Arun Somani Department of Electrical and Computer Engineering Iowa State University Ames, IA 50011 Email: {jxding,arun}@iastate.edu Abstract--The current energy infrastructure heavily

187

Light Water Reactor Sustainability Program Integrated Program Plan  

SciTech Connect (OSTI)

Nuclear power has safely, reliably, and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. Domestic demand for electrical energy is expected to experience a 31% growth from 2009 to 2035. At the same time, most of the currently operating nuclear power plants will begin reaching the end of their initial 20-year extension to their original 40-year operating license for a total of 60 years of operation. Figure E-1 shows projected nuclear energy contribution to the domestic generating capacity. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to decline—even with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary in 2009. The U.S. Department of Energy Office of Nuclear Energy’s Research and Development Roadmap (Nuclear Energy Roadmap) organizes its activities around four objectives that ensure nuclear energy remains a compelling and viable energy option for the United States. The four objectives are as follows: (1) develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of the current reactors; (2) develop improvements in the affordability of new reactors to enable nuclear energy to help meet the Administration’s energy security and climate change goals; (3) develop sustainable nuclear fuel cycles; and (4) understand and minimize the risks of nuclear proliferation and terrorism. The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1. This document summarizes the LWRS Program’s plans.

McCarthy, Kathryn A. [INL; Busby, Jeremy [ORNL; Hallbert, Bruce [INL; Bragg-Sitton, Shannon [INL; Smith, Curtis [INL; Barnard, Cathy [INL

2014-04-01T23:59:59.000Z

188

Light Water Reactor Sustainability Program Integrated Program Plan  

SciTech Connect (OSTI)

Nuclear power has safely, reliably, and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. Domestic demand for electrical energy is expected to experience a 31% growth from 2009 to 2035. At the same time, most of the currently operating nuclear power plants will begin reaching the end of their initial 20-year extension to their original 40-year operating license for a total of 60 years of operation. Figure E-1 shows projected nuclear energy contribution to the domestic generating capacity. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to decline - even with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary in 2009. The U.S. Department of Energy Office of Nuclear Energy's Research and Development Roadmap (Nuclear Energy Roadmap) organizes its activities around four objectives that ensure nuclear energy remains a compelling and viable energy option for the United States. The four objectives are as follows: (1) develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of the current reactors; (2) develop improvements in the affordability of new reactors to enable nuclear energy to help meet the Administration's energy security and climate change goals; (3) develop sustainable nuclear fuel cycles; and (4) understand and minimize the risks of nuclear proliferation and terrorism. The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1. This document summarizes the LWRS Program's plans.

George Griffith; Robert Youngblood; Jeremy Busby; Bruce Hallbert; Cathy Barnard; Kathryn McCarthy

2012-01-01T23:59:59.000Z

189

Light Water Reactor Sustainability Program Integrated Program Plan  

SciTech Connect (OSTI)

Nuclear power has safely, reliably, and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. Domestic demand for electrical energy is expected to experience a 31% growth from 2009 to 2035. At the same time, most of the currently operating nuclear power plants will begin reaching the end of their initial 20-year extension to their original 40-year operating license for a total of 60 years of operation. Figure E-1 shows projected nuclear energy contribution to the domestic generating capacity. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to decline—even with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary in 2009. The U.S. Department of Energy Office of Nuclear Energy’s Research and Development Roadmap (Nuclear Energy Roadmap) organizes its activities around four objectives that ensure nuclear energy remains a compelling and viable energy option for the United States. The four objectives are as follows: (1) develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of the current reactors; (2) develop improvements in the affordability of new reactors to enable nuclear energy to help meet the Administration’s energy security and climate change goals; (3) develop sustainable nuclear fuel cycles; and (4) understand and minimize the risks of nuclear proliferation and terrorism. The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1. This document summarizes the LWRS Program’s plans.

Kathryn McCarthy; Jeremy Busby; Bruce Hallbert; Shannon Bragg-Sitton; Curtis Smith; Cathy Barnard

2013-04-01T23:59:59.000Z

190

Integrated Assessment Plan Template and Operational Demonstration for SPIDERS Phase 2: Fort Carson  

SciTech Connect (OSTI)

This document contains the Integrated Assessment Plan (IAP) for the Phase 2 Operational Demonstration (OD) of the Smart Power Infrastructure Demonstration for Energy Reliability (SPIDERS) Joint Capability Technology Demonstration (JCTD) project. SPIDERS will be conducted over a three year period with Phase 2 being conducted at Fort Carson, Colorado. This document includes the Operational Demonstration Execution Plan (ODEP) and the Operational Assessment Execution Plan (OAEP), as approved by the Operational Manager (OM) and the Integrated Management Team (IMT). The ODEP describes the process by which the OD is conducted and the OAEP describes the process by which the data collected from the OD is processed. The execution of the OD, in accordance with the ODEP and the subsequent execution of the OAEP, will generate the necessary data for the Quick Look Report (QLR) and the Utility Assessment Report (UAR). These reports will assess the ability of the SPIDERS JCTD to meet the four critical requirements listed in the Implementation Directive (ID).

Barr, Jonathan L.; Tuffner, Francis K.; Hadley, Mark D.; Kreyling, Sean J.; Schneider, Kevin P.

2013-09-01T23:59:59.000Z

191

Fact Sheet - Renewable Resource Integration Action Plan - June 20, 2006  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicy andExsolutionFES6FYRANDOM DRUG TESTING TheMay 2012 BIn August,On

192

Couplingbased Integration Testing \\Lambda Zhenyi Jin y and A. Jefferson Offutt  

E-Print Network [OSTI]

coverage crite­ ria, routine aspects of testing, particularly at the inte­ gration level. Formal coverageCoupling­based Integration Testing \\Lambda Zhenyi Jin y and A. Jefferson Offutt ISSE Department, 4A testing is an important part of the test­ ing process, but few integration testing techniques have been

Offutt, Jeff

193

Power-Aware SoC Test Planning for Effective Utilization of Port-Scalable Testers  

E-Print Network [OSTI]

circuits contain embedded cores with different scan frequen- cies. To better meet the test requirements if the resulting test access architecture reduces the bit-width used to access it. We present a scalable test planning technique that exploits port scalability of testers to reduce SoC test time. We compare

Chakrabarty, Krishnendu

194

Modular Operational Test Plans for Inferences on Software Reliability Based on a Markov Model  

E-Print Network [OSTI]

Modular Operational Test Plans for Inferences on Software Reliability Based on a Markov Model reliabilities. An operational test procedure is considered in which only the individual modules are tested and the system is considered acceptable if, and only if, no failures are observed. The minimum number of tests

Mazumdar, Mainak

195

Integrated Disposal Facility FY 2012 Glass Testing Summary Report  

SciTech Connect (OSTI)

PNNL is conducting work to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility for Hanford immobilized low-activity waste (ILAW). Before the ILAW can be disposed, DOE must conduct a performance assessment (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program, PNNL is implementing a strategy, consisting of experimentation and modeling, to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. Key activities in FY12 include upgrading the STOMP/eSTOMP codes to do near-field modeling, geochemical modeling of PCT tests to determine the reaction network to be used in the STOMP codes, conducting PUF tests on selected glasses to simulate and accelerate glass weathering, developing a Monte Carlo simulation tool to predict the characteristics of the weathered glass reaction layer as a function of glass composition, and characterizing glasses and soil samples exhumed from an 8-year lysimeter test. The purpose of this report is to summarize the progress made in fiscal year (FY) 2012 and the first quarter of FY 2013 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of LAW glasses.

Pierce, Eric M.; Kerisit, Sebastien N.; Krogstad, Eirik J.; Burton, Sarah D.; Bjornstad, Bruce N.; Freedman, Vicky L.; Cantrell, Kirk J.; Snyder, Michelle MV; Crum, Jarrod V.; Westsik, Joseph H.

2013-03-29T23:59:59.000Z

196

Project W-314 specific test and evaluation plan for AZ tank farm upgrades  

SciTech Connect (OSTI)

The purpose of this Specific Test and Evaluation Plan (STEP) is to provide a detailed written plan for the systematic testing of modifications made by the addition of the SN-631 transfer line from the AZ-O1A pit to the AZ-02A pit by the W-314 Project. The STEP develops the outline for test procedures that verify the system`s performance to the established Project design criteria. The STEP is a lower tier document based on the W-314 Test and Evaluation P1 an (TEP). Testing includes Validations and Verifications (e.g., Commercial Grade Item Dedication activities, etc), Factory Tests and Inspections (FTIs), installation tests and inspections, Construction Tests and Inspections (CTIs), Acceptance Test Procedures (ATPs), Pre-Operational Test Procedures (POTPs), and Operational Test Procedures (OTPs). The STEP will be utilized in conjunction with the TEP for verification and validation.

Hays, W.H.

1998-08-12T23:59:59.000Z

197

CPP-603 Underwater Fuel Storage Facility Site Integrated Stabilization Management Plan (SISMP), Volume I  

SciTech Connect (OSTI)

The CPP-603 Underwater Fuel Storage Facility (UFSF) Site Integrated Stabilization Management Plan (SISMP) has been constructed to describe the activities required for the relocation of spent nuclear fuel (SNF) from the CPP-603 facility. These activities are the only Idaho National Engineering Laboratory (INEL) actions identified in the Implementation Plan developed to meet the requirements of the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-1 to the Secretary of Energy regarding an improved schedule for remediation in the Defense Nuclear Facilities Complex. As described in the DNFSB Recommendation 94-1 Implementation Plan, issued February 28, 1995, an INEL Spent Nuclear Fuel Management Plan is currently under development to direct the placement of SNF currently in existing INEL facilities into interim storage, and to address the coordination of intrasite SNF movements with new receipts and intersite transfers that were identified in the DOE SNF Programmatic and INEL Environmental Restoration and Waste Management Environmental Impact Statement Record, of Decision. This SISMP will be a subset of the INEL Spent Nuclear Fuel Management Plan and the activities described are being coordinated with other INEL SNF management activities. The CPP-603 relocation activities have been assigned a high priority so that established milestones will be meet, but there will be some cases where other activities will take precedence in utilization of available resources. The Draft INEL Site Integrated Stabilization Management Plan (SISMP), INEL-94/0279, Draft Rev. 2, dated March 10, 1995, is being superseded by the INEL Spent Nuclear Fuel Management Plan and this CPP-603 specific SISMP.

Denney, R.D.

1995-10-01T23:59:59.000Z

198

Pilot-scale treatability test plan for the 200-UP-1 groundwater Operable Unit  

SciTech Connect (OSTI)

This document presents the treatability test plan for pilot-scale pump and treat testing at the 200-UP-1 Operable Unit. This treatability test plan has been prepared in response to an agreement between the US Department of Energy, the US Environmental Protection Agency, and the Washington State Department of Ecology, as documented in Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1989a) Change Control Form M-13-93-03 (Ecology et al. 1994). The agreement also requires that, following completion of the activities described in this test plan, a 200-UP-1 Operable Unit interim remedial measure (IRM) proposed plan be developed for use in preparing an interim action record of decision (ROD). The IRM Proposed Plan will be supported by the results of the testing described in this treatability test plan, as well as by other 200-UP-1 Operable Unit activities (e.g., limited field investigation, development of a qualitative risk assessment). Once issued, the interim action ROD will specify the interim action for groundwater contamination at the 200-UP-1 Operable Unit. The approach discussed in this treatability test plan is to conduct a pilot-scale pump and treat test for the contaminant plume associated with the 200-UP-1 Operable Unit. Primary contaminants of concern are uranium and technetium-99; the secondary contaminant of concern is nitrate. The pilot-scale treatability testing presented in this test plan has as its primary purpose to assess the performance of aboveground treatment systems with respect to the ability to remove the primary contaminants in groundwater withdrawn from the contaminant plume.

Wittreich, C.D.

1994-05-01T23:59:59.000Z

199

Test plan for the irradiation of nonmetallic materials.  

SciTech Connect (OSTI)

A comprehensive test program to evaluate nonmetallic materials use in the Hanford tank farms is described in detail. This test program determines the effects of simultaneous multiple stressors at reasonable conditions on in-service configuration components by engineering performance testing.

Brush, Laurence H.; Farnum, Cathy Ottinger; Dahl, M. [ARES Corporation, Richland, WA; Joslyn, C. C. [Washington River Protection Solutions, Richland, WA; Venetz, T. J. [Washington River Protection Solutions, Richland, WA

2013-05-01T23:59:59.000Z

200

Test plan for the irradiation of nonmetallic materials.  

SciTech Connect (OSTI)

A comprehensive test program to evaluate nonmetallic materials use in the Hanford Tank Farms is described in detail. This test program determines the effects of simultaneous multiple stressors at reasonable conditions on in-service configuration components by engineering performance testing.

Brush, Laurence H.; Farnum, Cathy Ottinger; Gelbard, Fred; Dahl, M. [ARES Corporation, Richland, WA; Joslyn, C. C. [Washington River Protection Solutions, Richland, WA; Venetz, T. J. [Washington River Protection Solutions, Richland, WA

2013-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "integrated test plan" 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

Beta Test Plan for Advanced Inverters Interconnecting Distributed Resources with Electric Power Systems  

SciTech Connect (OSTI)

This document provides a preliminary (beta) test plan for grid interconnection systems of advanced inverter-based DERs. It follows the format and methodology/approach established by IEEE Std 1547.1, while incorporating: 1. Upgraded tests for responses to abnormal voltage and frequency, and also including ride-through. 2. A newly developed test for voltage regulation, including dynamic response testing. 3. Modified tests for unintentional islanding, open phase, and harmonics to include testing with the advanced voltage and frequency response functions enabled. Two advanced inverters, one single-phase and one three-phase, were tested under the beta test plan. These tests confirmed the importance of including tests for inverter dynamic response, which varies widely from one inverter to the next.

Hoke, A.; Chakraborty, S.; Basso, T.; Coddington, M.

2014-01-01T23:59:59.000Z

202

Closure Plan for the Area 3 Radioactive Waste Management Site at the Nevada Test Site  

SciTech Connect (OSTI)

The Area 3 Radioactive Waste Management Site (RMWS) at the Nevada Test Site (NTS) is managed and operated by National Security Technologies, LLC (NSTec) for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This document is the first update of the interim closure plan for the Area 3 RWMS, which was presented in the Integrated Closure and Monitoring Plan (ICMP) (DOE, 2005). The format and content of this plan follows the Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans (DOE, 1999a). The major updates to the plan include a new closure date, updated closure inventory, the new institutional control policy, and the Title II engineering cover design. The plan identifies the assumptions and regulatory requirements, describes the disposal sites and the physical environment in which they are located, presents the design of the closure cover, and defines the approach and schedule for both closing and monitoring the site. The Area 3 RWMS accepts low-level waste (LLW) from across the DOE Complex in compliance with the NTS Waste Acceptance Criteria (NNSA/NSO, 2006). The Area 3 RWMS accepts both packaged and unpackaged unclassified bulk LLW for disposal in subsidence craters that resulted from deep underground tests of nuclear devices in the early 1960s. The Area 3 RWMS covers 48 hectares (119 acres) and comprises seven subsidence craters--U-3ax, U-3bl, U-3ah, U-3at, U-3bh, U-3az, and U-3bg. The area between craters U-3ax and U-3bl was excavated to form one large disposal unit (U-3ax/bl); the area between craters U-3ah and U-3at was also excavated to form another large disposal unit (U-3ah/at). Waste unit U-3ax/bl is closed; waste units U-3ah/at and U-3bh are active; and the remaining craters, although currently undeveloped, are available for disposal of waste if required. This plan specifically addresses the closure of the U-3ah/at and the U-3bh LLW units. A final closure cover has been placed on unit U-3ax/bl (Corrective Action Unit 110) at the Area 3 RWMS. Monolayer-evapotranspirative closure cover designs for the U-3ah/at and U-3bh units are provided in this plan. The current-design closure cover thickness is 3 meters (10 feet). The final design cover will have an optimized cover thickness, which is expected to be less than 3 m (10 ft). Although waste operations at the Area 3 RWMS have ceased at the end of June 2006, disposal capacity is available for future disposals at the U-3ah/at and U-3bh units. The Area 3 RWMS is expected to start closure activities in fiscal year 2025, which include the development of final performance assessment and composite analysis documents, closure plan, closure cover design for construction, cover construction, and initiation of the post-closure care and monitoring activities. Current monitoring at the Area 3 RWMS includes monitoring the cover of the closed mixed waste unit U-3ax/bl as required by the Nevada Department of Environmental Protection, and others required under federal regulations and DOE orders. Monitoring data, collected via sensors and analysis of samples, are needed to evaluate radiation doses to the general public, for performance assessment maintenance, to demonstrate regulatory compliance, and to evaluate the actual performance of the RWMSs. Monitoring provides data to ensure the integrity and performance of waste disposal units. The monitoring program is designed to forewarn management and regulators of any failure and need for mitigating actions. The plan describes the program for monitoring direct radiation, air, vadose zone, biota, groundwater, meteorology, and subsidence. The requirements of post-closure cover maintenance and monitoring will be determined in the final closure plan.

NSTec Environmental Management

2007-09-01T23:59:59.000Z

203

Integrated Energy-Water Planning in the Western and Texas Interconnections  

SciTech Connect (OSTI)

While long-term regional electricity transmission planning has traditionally focused on cost, infrastructure utilization, and reliability, issues concerning the availability of water represent an emerging issue. Thermoelectric expansion must be considered in the context of competing demands from other water use sectors balanced with fresh and non-fresh water supplies subject to climate variability. An integrated Energy-Water Decision Support System (DSS) is being developed that will enable planners in the Western and Texas Interconnections to analyze the potential implications of water availability and cost for long-range transmission planning. The project brings together electric transmission planners (Western Electricity Coordinating Council and Electric Reliability Council of Texas) with western water planners (Western Governors’ Association and the Western States Water Council). This paper lays out the basic framework for this integrated Energy-Water DSS.

Vincent Tidwell; John Gasper; Robert Goldstein; Jordan Macknick; Gerald Sehlke; Michael Webber; Mark Wigmosta

2013-07-01T23:59:59.000Z

204

Dual Axis Radiographic Hydrodynamic Test Facility mitigation action plan. Annual report for 1998  

SciTech Connect (OSTI)

This Mitigation Action Plan Annual Report (MAPAR) has been prepared as part of implementing the Dual Axis Radiographic Hydrodynamic Test Facility (DARHT) Mitigation Action Plan (MAP) to protect workers, soils, water, and biotic and cultural resources in and around the facility.

Haagenstad, T.

1999-01-15T23:59:59.000Z

205

Planning, Execution, and Analysis of the Meridian UAS Flight Test Program Including System and Parameter Identification  

E-Print Network [OSTI]

The purpose of this Master Thesis is to present the flight test procedures, planning, and analysis including system identification, parameter identification, and drag calculations of the Meridian UAS. The system identification is performed using...

Tom, Jonathan

2010-04-27T23:59:59.000Z

206

Electric utility system planning studies for OTEC power integration. Final report  

SciTech Connect (OSTI)

Florida Power Corporation (FPC) conducted an evaluation of the possible integration of OTEC into the FPC system. Existing system planning procedures, assumptions, and corporate financial criteria for planning new generating capacity were used without modification. A baseline configuration for an OTEC plant was developed for review with standard planning procedures. The OTEC plant characteristics and costs were incorporated in considerable detail. These basic inputs were examined using the FPC system planning methods. It was found that with the initial set of conditions, OTEC would not be economically viable. Using the same system planning procedures, a number of adjustments were made to the key study assumptions. It was found that two considerations dominate the analysis; the assumed rate of fuel cost escalation, and the projected capital cost of the OTEC plant. The analysis produced a parametric curve: on one hand, if fuel costs were to escalate at a rate greater than assumed (12% vs the assumed 5% for coal), and if no change were made to the OTEC input assumptions, the basic economic competitive criteria would be equivalent to the principal alternative, coal fueled plants. Conversely, if the projected cost of the OTEC plant were to be reduced from the assumed $2256/kW to $1450/kW, the economic competitiveness criterion would be satisfied. After corporate financial analysis, it was found that even if the cost competitive criterion were to be reached, the plan including OTEC could not be financed by Florida Power Corporation. Since, under the existing set of conditions for financing new plant capital requirements, FPC could not construct an OTEC plant, some other means of ownership would be necessary to integrate OTEC into the FPC system. An alternative such as a third party owning the plant and selling power to FPC, might prove attractive. (WHK)

None

1980-11-30T23:59:59.000Z

207

Test plan for high-burnup fuel cladding behavior under loss-of- coolant accident conditions  

SciTech Connect (OSTI)

Excessive oxidation, hydriding, and extensive irradiation damage occur in high-burnup fuel cladding, and as result, mechanical properties of high-burnup fuels are degraded significantly. This may influence the current fuel cladding failure limits for loss-of- coolant-accident (LOCA) situations, which are based on fuel cladding behavior for zero burnup. To avoid cladding fragmentation and fuel dispersal during a LOCA, 10 CFR 50.46 requires that peak cladding temperature shall not exceed 1204 degrees C (2200 degrees F) and that total oxidation of the fuel cladding nowhere exceeds 0.17 times total cladding thickness before oxidation. Because of the concern, a new experimental program to investigate high-burnup fuel cladding behavior under LOCA situations has been initiated under the sponsorship of the U.S. Nuclear Regulatory Commission. A hot-cell test plan to investigate single-rod behavior under simulated LOCA conditions is described in this paper. In the meantime, industry fuel design and operating conditions are expected to undergo further changes as more advanced cladding materials are developed. Under these circumstances, mechanical properties of high-burnup fuel cladding require further investigation so that results from studies on LOCA, reactivity- initiated-accident (RIA), operational transient, and power-ramping situations, can be extrapolated to modified or advanced cladding materials and altered irradiation conditions without repeating major integral experiments in test reactors. To provide the applicable data base and mechanistic understanding, tests will be conducted to determine dynamic and static fracture toughness and tensile properties. Background and rationale for selecting the specific mechanical properties tests are also described.

Chung, H.M.; Neimark, L.A.; Kassner, T.F.

1996-10-01T23:59:59.000Z

208

Microsoft Word - DOE HBU Demo - Revised Test Plan Report - Rev...  

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

Development, and Demonstration RTN Removable Top Nozzle RX Recrystallized SCC Stress Corrosion Cracking SE Safety Evaluation SET Separate Effects Test SNF Spent Nuclear Fuel SSC...

209

Model-Based Testing for the Second Generation of Integrated Modular Avionics Christof Efkemann, Jan Peleska  

E-Print Network [OSTI]

activities regarding automated testing of Integrated Modular Avionics controllers in the European research, specialised electronics devices, many of them with cus- tom interfaces. In the Integrated Modular AvionicsModel-Based Testing for the Second Generation of Integrated Modular Avionics Christof Efkemann, Jan

Peleska, Jan - Fachbereich 3

210

Moving Granular-Bed Filter Development Program, Option 1 - Component Test Facilities - Test Plan; topical report, September 8, 1995  

SciTech Connect (OSTI)

A test plan has been devised for Option 1 Contract period that focuses on the remaining SMGBF technical issues for the purpose of optimizing the SMGBF performance and generating key process performance data needed to promote the continued development of the technology. These technical issues have been identified and ranked in the Task 8, Technical Tradeoffs and Issues Report, submitted to DOE in May, 1994. Three activities are defined in this test plan to address the key issues identified: the first activity performs engineering modeling and design evaluation to Support the test activities; the second activity is directed toward SMGBF cold flow model testing; and the third activity is directed toward high- temperature, high-pressure (HTHP) SMGBF testing. All of the activities are directed toward Recycle SMGBF, although much of it also applies to Once-Through SMGBF.

NONE

1997-12-31T23:59:59.000Z

211

Gearbox Reliability Collaborative Phase 3 Gearbox 2 Test Plan  

SciTech Connect (OSTI)

Gearboxes in wind turbines have not been achieving their expected design life even though they commonly meet or exceed the design criteria specified in current design standards. One of the basic premises of the National Renewable Energy Laboratory (NREL) Gearbox Reliability Collaborative (GRC) is that the low gearbox reliability results from the absence of critical elements in the design process or insufficient design tools. Key goals of the GRC are to improve design approaches and analysis tools and to recommend practices and test methods resulting in improved design standards for wind turbine gearboxes that lower the cost of energy (COE) through improved reliability. The GRC uses a combined gearbox testing, modeling and analysis approach, along with a database of information from gearbox failures collected from overhauls and investigation of gearbox condition monitoring techniques to improve wind turbine operations and maintenance practices. Testing of Gearbox 2 (GB2) using the two-speed turbine controller that has been used in prior testing. This test series will investigate non-torque loads, high-speed shaft misalignment, and reproduction of field conditions in the dynamometer. This test series will also include vibration testing using an eddy-current brake on the gearbox's high speed shaft.

Link, H.; Keller, J.; Guo, Y.; McNiff, B.

2013-04-01T23:59:59.000Z

212

Test and evaluation plan for the composite bridge  

SciTech Connect (OSTI)

Polymer matrix composites (PMC) are entering the nation`s infrastructure as alternatives to conventional materials. Working with the Federal Highway Administration and Department of Energy, the Idaho National Engineering and Environmental Laboratory is testing and evaluating a PMC structure for use in bridge rehabilitation and replacement. A 30-foot PMC bridge, designed and built by Lockheed Martin Missile and Space, will be field tested in Idaho. The design of this bridge represents simple support bridges in the 120-foot span category. This report describes the construction, transportation, installation, testing, and material properties for this PMC structure.

Rodriguez, J.G.; Dumlao, C.; Ciolko, A.T.; Pfister, T.J.; Schmeckpeper, E.R.

1997-04-01T23:59:59.000Z

213

Test plan for thermogravimetric analyses of BWR spent fuel oxidation  

SciTech Connect (OSTI)

Preliminary studies indicated the need for additional low-temperature spent fuel oxidation data to determine the behavior of spent fuel as a waste form for a tuffy repository. Short-term thermogravimetric analysis tests were recommended in a comprehensive technical approach as the method for providing scoping data that could be used to (1) evaluate the effects of variables such as moisture and burnup on the oxidation rate, (2) determine operative mechanisms, and (3) guide long-term, low-temperature oxidation testing. The initial test series studied the temperature and moisture effects on pressurized water reactor fuel as a function of particle and grain size. This document presents the test matrix for studying the oxidation behavior of boiling water reactor fuel in the temperature range of 140 to 225{degree}C. 17 refs., 7 figs., 3 tabs.

Einziger, R.E.

1988-12-01T23:59:59.000Z

214

An Integrated Automatic Test Data Generation System A. Jefferson Offutt \\Lambda  

E-Print Network [OSTI]

An Integrated Automatic Test Data Generation System A. Jefferson Offutt \\Lambda Department of Computer Science Clemson University Clemson, SC 29634 January 21, 1996 Abstract The Godzilla automatic test data generator is an integrated collection of tools that implements a relatively new test data

Offutt, Jeff

215

An Integrated Automatic Test Data Generation System A. Je erson O utt  

E-Print Network [OSTI]

An Integrated Automatic Test Data Generation System A. Je erson O utt Department of Computer Science Clemson University Clemson, SC 29634 January 21, 1996 Abstract The Godzilla automatic test data generator is an integrated collection of tools that implements a relatively new test data generation method

Offutt, Jeff

216

Nevada Test Site, site treatment plan 1999 annual update  

SciTech Connect (OSTI)

A Site Treatment Plan (STP) is required for facilities at which the US Department of Energy Nevada Operations Office (DOE/NV) generates or stores mixed waste (MW), defined by the Federal Facility Compliance Act (FFC Act) as waste containing both a hazardous waste subject to the Resource Conservation and Recovery Act (RCRA) and a radioactive material subject to the Atomic Energy Act. This STP was written to identify specific treatment facilities for treating DOE/NV generated MW and provides proposed implementation schedules. This STP was approved by the Nevada Division of Environmental Protection (NDEP) and provided the basis for the negotiation and issuance of the FFC Act Consent Order (CO) dated March 6, 1996, and revised June 15, 1998. The FFC Act CO sets forth stringent regulatory requirements to comply with the implementation of the STP.

NONE

1999-03-01T23:59:59.000Z

217

Development of an Integrated Waste Plan for Chalk River Laboratories - 13376  

SciTech Connect (OSTI)

To further its Strategic Planning, the Atomic Energy of Canada Limited (AECL) required an effective approach to developing a fully integrated waste plan for its Chalk River Laboratories (CRL) site. Production of the first Integrated Waste Plan (IWP) for Chalk River was a substantial task involving representatives from each of the major internal stakeholders. Since then, a second revision has been produced and a third is underway. The IWP remains an Interim IWP until all gaps have been resolved and all pathways are at an acceptable level of detail. Full completion will involve a number of iterations, typically annually for up to six years. The end result of completing this process is a comprehensive document and supporting information that includes: - An Integrated Waste Plan document summarizing the entire waste management picture in one place; - Details of all the wastes required to be managed, including volume and timings by waste stream; - Detailed waste stream pathway maps for the whole life-cycle for each waste stream to be managed from pre-generation planning through to final disposition; and - Critical decision points, i.e. decisions that need to be made and timings by when they need to be made. A waste inventory has been constructed that serves as the master reference inventory of all waste that has been or is committed to be managed at CRL. In the past, only the waste that is in storage has been effectively captured, and future predictions of wastes requiring to be managed were not available in one place. The IWP has also provided a detailed baseline plan at the current level of refinement. Waste flow maps for all identified waste streams, for the full waste life cycle complete to disposition have been constructed. The maps identify areas requiring further development, and show the complexities and inter-relationships between waste streams. Knowledge of these inter-dependencies is necessary in order to perform effective options studies for enabling facilities that may be necessary for multiple related waste streams. The next step is to engage external stakeholders in the optioneering work required to provide enhanced confidence that the path forward identified within future iterations of the IWP will be acceptable to all. (authors)

Jones, L. [Atomic Energy of Canada Limited Chalk River, Ontario (Canada)] [Atomic Energy of Canada Limited Chalk River, Ontario (Canada)

2013-07-01T23:59:59.000Z

218

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

219

Fuel Cell Technologies Office Multi-Year Research, Development, and Demonstration Plan- Section 5.0 Systems Integration  

Broader source: Energy.gov [DOE]

Systems Integration section of the Fuel Cell Technologies Office Multi-Year Research, Development, and Demonstration Plan; updated July 2013. This plan includes goals, objectives, technical targets, tasks, and schedules for the Office of Energy Efficiency and Renewable Energy's contribution to the DOE Hydrogen and Fuel Cells Program.

220

300-FF-1 physical separations CERCLA treatability test plan. Revision 1  

SciTech Connect (OSTI)

This test plan describes specifications, responsibilities, and general procedures to be followed to conduct physical separations soil treatability tests in the north process pond of the 300-FF-1 Operable Unit at the Hanford Site. The overall objective of these tests is to evaluate the use of physical separations systems as a means of concentrating chemical and radioactive contaminants into fine soil fractions, and thereby minimizing waste volumes. If successful, the technology could be applied to clean up millions of cubic meters of contaminated soils at Hanford and other sites. In this document, physical separations refers to a simple and comparatively low cost technology to potentially achieve a significant reduction in the volume of contaminated soils without the use of chemical processes. Removal of metals and radioactive contaminants from the fine fraction of soils may require additional treatment such as chemical extraction, electromagnetic separation, or stabilization. Investigations/testing of these technologies are recommended to assess the economic and technical feasibility of additional treatment, but are not within the scope of this test. This plan provides guidance and specifications for two proposed treatability tests: one to be conducted by Westinghouse Hanford Company; and another proposed as competitive bid service contract. The main body of this test plan discusses the tests in general and items that are common to both tests. Attachment A discusses in detail the EPA system test and Attachment B discusses the vendor test.

Not Available

1993-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "integrated test plan" 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

Test Plan of the Anticipatory Wirelss Sensor Network for the Critical Energy Infrastructure  

SciTech Connect (OSTI)

The test plan for the performance of the Anticipatory Wireless Sensor Network (A-WSN) is presented. The results of the test campaigns will be obtained after actual measurements are taken in the field with the Wireless Sensor Network developed by The Innovation Center-Eaton Corp., and the Anticipatory algorithms developed by ORNL.

Carlos Rentel

2006-09-01T23:59:59.000Z

222

300 Area Integrated Field-Scale Subsurface Research Challenge (IFRC) Field Site Management Plan  

SciTech Connect (OSTI)

Pacific Northwest National Laboratory (PNNL) has established the 300 Area Integrated Field-Scale Subsurface Research Challenge (300 Area IFRC) on the Hanford Site in southeastern Washington State for the U.S. Department of Energy’s (DOE) Office of Biological and Environmental Research (BER) within the Office of Science. The project is funded by the Environmental Remediation Sciences Division (ERSD). The purpose of the project is to conduct research at the 300 IFRC to investigate multi-scale mass transfer processes associated with a subsurface uranium plume impacting both the vadose zone and groundwater. The management approach for the 300 Area IFRC requires that a Field Site Management Plan be developed. This is an update of the plan to reflect the installation of the well network and other changes.

Freshley, Mark D.

2008-12-31T23:59:59.000Z

223

NREL Next Generation Drivetrain: Mechanical Design and Test Plan (Poster)  

SciTech Connect (OSTI)

The Department of Energy and industry partners are sponsoring a $3m project for design and testing of a 'Next Generation' wind turbine drivetrain at the National Renewable Energy Laboratory (NREL). This poster focuses on innovative aspects of the gearbox design, completed as part of an end-to-end systems engineering approach incorporating innovations that increase drivetrain reliability, efficiency, torque density and minimize capital cost.

Keller, J.; Halse, C.

2014-05-01T23:59:59.000Z

224

DOUBLE TRACKS Test Site interim corrective action plan  

SciTech Connect (OSTI)

The DOUBLE TRACKS site is located on Range 71 north of the Nellis Air Force Range, northwest of the Nevada Test Site (NTS). DOUBLE TRACKS was the first of four experiments that constituted Operation ROLLER COASTER. On May 15, 1963, weapons-grade plutonium and depleted uranium were dispersed using 54 kilograms of trinitrotoluene (TNT) explosive. The explosion occurred in the open, 0.3 m above the steel plate. No fission yield was detected from the test, and the total amount of plutonium deposited on the ground surface was estimated to be between 980 and 1,600 grams. The test device was composed primarily of uranium-238 and plutonium-239. The mass ratio of uranium to plutonium was 4.35. The objective of the corrective action is to reduce the potential risk to human health and the environment and to demonstrate technically viable and cost-effective excavation, transportation, and disposal. To achieve these objectives, Bechtel Nevada (BN) will remove soil with a total transuranic activity greater then 200 pCI/g, containerize the soil in ``supersacks,`` transport the filled ``supersacks`` to the NTS, and dispose of them in the Area 3 Radioactive Waste Management Site. During this interim corrective action, BN will also conduct a limited demonstration of an alternative method for excavation of radioactive near-surface soil contamination.

NONE

1996-06-01T23:59:59.000Z

225

A planning study of simultaneous integrated boost with forward IMRT for multiple brain metastases  

SciTech Connect (OSTI)

The objective of this study was to evaluate the dose conformity and feasibility of whole-brain radiotherapy with a simultaneous integrated boost by forward intensity-modulated radiation therapy in patients with 1 to 3 brain metastases. Forward intensity-modulated radiation therapy plans were generated for 10 patients with 1 to 3 brain metastases on Pinnacle 6.2 Treatment Planning System. The prescribed dose was 30 Gy to the whole brain (planning target volume [PTV]{sub wbrt}) and 40 Gy to individual brain metastases (PTV{sub boost}) simultaneously, and both doses were given in 10 fractions. The maximum diameters of individual brain metastases ranged from 1.6 to 6 cm, and the summated PTVs per patient ranged from 1.62 to 69.81 cm{sup 3}. Conformity and feasibility were evaluated regarding conformation number and treatment delivery time. One hundred percent volume of the PTV{sub boost} received at least 95% of the prescribed dose in all cases. The maximum doses were less than 110% of the prescribed dose to the PTV{sub boost}, and all of the hot spots were within the PTV{sub boost}. The volume of the PTV{sub wbrt} that received at least 95% of the prescribed dose ranged from 99.2% to 100%. The mean values of conformation number were 0.682. The mean treatment delivery time was 2.79 minutes. Ten beams were used on an average in these plans. Whole-brain radiotherapy with a simultaneous integrated boost by forward intensity-modulated radiation therapy in 1 to 3 brain metastases is feasible, and treatment delivery time is short.

Liang, Xiaodong, E-mail: lxdctopone@sina.com [Taizhou Central Hospital, Zhejiang Province (China); Ni, Lingqin; Hu, Wei; Chen, Weijun; Ying, Shenpeng; Gong, Qiangjun; Liu, Yanmei [Taizhou Central Hospital, Zhejiang Province (China)

2013-07-01T23:59:59.000Z

226

Report of the Integrated Program Planning Activity for the DOE Fusion Energy Sciences Program  

SciTech Connect (OSTI)

This report of the Integrated Program Planning Activity (IPPA) has been prepared in response to a recommendation by the Secretary of Energy Advisory Board that, ''Given the complex nature of the fusion effort, an integrated program planning process is an absolute necessity.'' We, therefore, undertook this activity in order to integrate the various elements of the program, to improve communication and performance accountability across the program, and to show the inter-connectedness and inter-dependency of the diverse parts of the national fusion energy sciences program. This report is based on the September 1999 Fusion Energy Sciences Advisory Committee's (FESAC) report ''Priorities and Balance within the Fusion Energy Sciences Program''. In its December 5,2000, letter to the Director of the Office of Science, the FESAC has reaffirmed the validity of the September 1999 report and stated that the IPPA presents a framework and process to guide the achievement of the 5-year goals listed in the 1999 report. The National Research Council's (NRC) Fusion Assessment Committee draft final report ''An Assessment of the Department of Energy's Office of Fusion Energy Sciences Program'', reviewing the quality of the science in the program, was made available after the IPPA report had been completed. The IPPA report is, nevertheless, consistent with the recommendations in the NRC report. In addition to program goals and the related 5-year, 10-year, and 15-year objectives, this report elaborates on the scientific issues associated with each of these objectives. The report also makes clear the relationships among the various program elements, and cites these relationships as the reason why integrated program planning is essential. In particular, while focusing on the science conducted by the program, the report addresses the important balances between the science and energy goals of the program, between the MFE and IFE approaches, and between the domestic and international aspects of the program. The report also outlines a process for establishing a database for the fusion research program that will indicate how each research element fits into the overall program. This database will also include near-term milestones associated with each research element, and will facilitate assessments of the balance within the program at different levels. The Office of Fusion Energy Sciences plans to begin assembling and using the database in the Spring of 2001 as we receive proposals from our laboratories and begin to prepare our budget proposal for Fiscal Year 2003.

None

2000-12-01T23:59:59.000Z

227

Test Methods Standing Technical Committee Strategic Plan - February 2012 |  

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 |Energy Usage »of Energy StrainClientDesignOffice -Template forTest MethodsDepartment of

228

Development and Testing of an Integrated Sandia Cooler Thermoelectric Device (SCTD).  

SciTech Connect (OSTI)

This report describes a FY14 effort to develop an integrated Sandia Cooler T hermoelectric D evice (SCTD) . The project included a review of feasible thermoelectric (TE) cooling applications, baseline performance testing of an existing TE device, analysis and design development of an integrated SCTD assembly, and performance measurement and validation of the integrated SCTD prototype.

Johnson, Terry A.; Staats, Wayne Lawrence,; Leick, Michael Thomas; Zimmerman, Mark D.; Radermacher, Reinhard; Martin, Cara; Nasuta, Dennis; Kalinowski, Paul; Hoffman, William

2014-12-01T23:59:59.000Z

229

Underground Test Area Quality Assurance Project Plan Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

This Quality Assurance Project Plan (QAPP) provides the overall quality assurance (QA) program requirements and general quality practices to be applied to the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Underground Test Area (UGTA) Sub-Project (hereafter the Sub-Project) activities. The requirements in this QAPP are consistent with DOE Order 414.1C, Quality Assurance (DOE, 2005); U.S. Environmental Protection Agency (EPA) Guidance for Quality Assurance Project Plans for Modeling (EPA, 2002); and EPA Guidance on the Development, Evaluation, and Application of Environmental Models (EPA, 2009). The QAPP Revision 0 supersedes DOE--341, Underground Test Area Quality Assurance Project Plan, Nevada Test Site, Nevada, Revision 4.

Irene Farnham

2011-05-01T23:59:59.000Z

230

Status and plans for a SRF accelerator test faciliy at Fermilab  

E-Print Network [OSTI]

A superconducting RF accelerator test facility is being constructed at Fermilab. The existing New Muon Lab (NML) building is being converted for this facility. The accelerator will consist of an electron gun, injector, beam acceleration section consisting of 3 TTF-type or ILC-type cryomodules, multiple downstream beam lines for testing diagnostics and conducting various beam tests, and a high power beam dump. When completed, it is envisioned that this facility will initially be capable of generating an 810 MeV electron beam with ILC beam intensity. Expansion plans of the facility are underway that will provide the capability to upgrade the accelerator to a total beam energy of 1.5 GeV. In addition to testing accelerator components, this facility will be used to test RF power equipment, instrumentation, LLRF and controls systems for future SRF accelerators such as the ILC and Project-X. This paper describes the current status and overall plans for this facility.

Leibfritz, J; Carlson, K; Chase, B; Church, M; Harms, E; Klebaner, A; Kucera, M; Lackey, S; Martinez, A; Nagaitsev, S; Nobrega, L; Piot, P; Reid, J; Wendt, M; Wesseln, S

2012-01-01T23:59:59.000Z

231

Innovative On-site Integrated Energy System Tested World Renewable Energy Congress VIII  

E-Print Network [OSTI]

and institutional settings. Recycling Waste Heat--a Key to Improving the Efficiency of Energy Supply In an eraInnovative On-site Integrated Energy System Tested World Renewable Energy Congress VIII August 29-September 3, 2004 Denver, Colorado #12;Innovative On-site Integrated Energy System Tested Jeanette B. Berry

Oak Ridge National Laboratory

232

Vertical Integration in Gasoline Supply: An Empirical Test of Raising Rivals' Costs  

E-Print Network [OSTI]

PWP-084 Vertical Integration in Gasoline Supply: An Empirical Test of Raising Rivals' Costs Justine-5180 www.ucei.org #12;Vertical Integration in Gasoline Supply: An Empirical Test of Raising Rivals' Costs gasoline prices. The 1997 acquisition of Unocal's West Coast refining and marketing assets by Tosco

California at Berkeley. University of

233

Deflagration studies on waste Tank 101-SY: Test plan  

SciTech Connect (OSTI)

Waste slurries produced during the recovery of plutonium and uranium from irradiated fuel are stored in underground storage tanks. While a variety of waste types have been generated, of particular concern are the wastes stored in Tank 101-SY. A slurry growth-gas evolution cycle has been observed since 1981. The waste consists of a thick slurry, consisting of a solution high in NaOH, NaNO{sub 3}, NaAlO{sub 2}, dissolved organic complexants (EDTA, HEDTA, NTA, and degradation products), other salts (sulfates and phosphates), and radionuclides (primarily cesium and strontium). During a gas release the major gaseous species identified include: hydrogen and nitrous oxide (N{sub 2}O). Significant amounts of nitrogen may also be present. Traces of ammonia, carbon oxides, and other nitrogen oxides are also detected. Air and water vapor are also present in the tank vapor space. The purpose of the deflagration study is to determine risks of the hydrogen, nitrous oxide, nitrogen, and oxygen system. To be determined are pressure and temperature as a function of composition of reacting gases and the concentration of gases before and after the combustion event. Analyses of gases after the combustion event will be restricted to those tests that had an initial concentration of {le}8% hydrogen. This information will be used to evaluate safety issues related to periodic slurry growth and flammable gas releases from Tank 101-SY. the conditions to be evaluated will simulate gases in the vapor space above the salt cake as well as gases that potentially are trapped in pockets within/under the waste. The deflagration study will relate experimental laboratory results to conditions in the existing tanks.

Cashdollar, K.L.; Zlochower, I.A.; Hertzberg, M.

1991-07-01T23:59:59.000Z

234

Integrated Performance Testing Workshop - Supplemental Materials (Scripts and Procedures)  

SciTech Connect (OSTI)

A variety of performance tests are described relating to: Material Transfers; Emergency Evacuation; Alarm Response Assessment; and an Enhanced Limited Scope Performance Test (ELSPT). Procedures are given for: nuclear material physical inventory and discrepancy; material transfers; and emergency evacuation.

Baum, Gregory A.

2014-02-01T23:59:59.000Z

235

Optimum combined test plans for systems and components JAYANT RAJGOPAL, MAINAK MAZUMDAR and SUBBA RAO V. MAJETY  

E-Print Network [OSTI]

Optimum combined test plans for systems and components JAYANT RAJGOPAL, MAINAK MAZUMDAR and SUBBA on the reliability of a system could be made on the basis of tests of its constituent components. Prior research in the area of system-based component testing has for the most part addressed the development of plans

Mazumdar, Mainak

236

Pilot-scale treatability test plan for the 200-BP-5 operable unit  

SciTech Connect (OSTI)

This document presents the treatability test plan for pilot-scale pump and treat testing at the 200-BP-5 Operable Unit. This treatability test plan has been prepared in response to an agreement between the U.S. Department of Energy (DOE), the U.S. Environmental Protection Agency (EPA), and the State of Washington Department of Ecology (Ecology), as documented in Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement, Ecology et al. 1989a) Change Control Form M-13-93-03 (Ecology et al. 1994) and a recent 200 NPL Agreement Change Control Form (Appendix A). The agreement also requires that, following completion of the activities described in this test plan, a 200-BP-5 Operable Unit Interim Remedial Measure (IRM) Proposed Plan be developed for use in preparing an Interim Action Record of Decision (ROD). The IRM Proposed Plan will be supported by the results of this treatability test plan, as well as by other 200-BP-5 Operable Unit activities (e.g., development of a qualitative risk assessment). Once issued, the Interim Action ROD will specify the interim action(s) for groundwater contamination at the 200-BP-5 Operable Unit. The treatability test approach is to conduct a pilot-scale pump and treat test for each of the two contaminant plumes associated with the 200-BP-5 Operable Unit. Primary contaminants of concern are {sup 99}Tc and {sup 60}Co for underwater affected by past discharges to the 216-BY Cribs, and {sup 90}Sr, {sup 239/240}Pu, and Cs for groundwater affected by past discharges to the 216-B-5 Reverse Well. The purpose of the pilot-scale treatability testing presented in this testplan is to provide the data basis for preparing an IRM Proposed Plan. To achieve this objective, treatability testing must: Assess the performance of groundwater pumping with respect to the ability to extract a significant amount of the primary contaminant mass present in the two contaminant plumes.

Not Available

1994-08-01T23:59:59.000Z

237

Test Plan for Long-Term Operation of a Ten-Cell High Temperature Electrolysis Stack  

SciTech Connect (OSTI)

This document defines a test plan for a long-term (2500 Hour) test of a ten-cell high-temperature electrolysis stack to be performed at INL during FY09 under the Nuclear Hydrogen Initiative. This test was originally planned for FY08, but was removed from our work scope as a result of the severe budget cuts in the FY08 NHI Program. The purpose of this test is to evaluate stack performance degradation over a relatively long time period and to attempt to identify some of the degradation mechanisms via post-test examination. This test will be performed using a planar ten-cell Ceramatec stack, with each cell having dimensions of 10 cm × 10 cm. The specific makeup of the stack will be based on the results of a series of shorter duration ten-cell stack tests being performed during FY08, funded by NGNP. This series of tests was aimed at evaluating stack performance with different interconnect materials and coatings and with or without brazed edge rails. The best performing stack from the FY08 series, in which five different interconnect/coating/edge rail combinations were tested, will be selected for the FY09 long-term test described herein.

James E. O'Brien; Carl M. Stoots; J. Stephen Herring

2008-07-01T23:59:59.000Z

238

Underground Test Area Project Waste Management Plan (Rev. No. 2, April 2002)  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Operations Office (NNSA/NV) initiated the UGTA Project to characterize the risk posed to human health and the environment as a result of underground nuclear testing activities at the Nevada Test Site (NTS). The UGTA Project investigation sites have been grouped into Corrective Action Units (CAUs) in accordance with the most recent version of the Federal Facility Agreement and Consent Order. The primary UGTA objective is to gather data to characterize the groundwater aquifers beneath the NTS and adjacent lands. The investigations proposed under the UGTA program may involve the drilling and sampling of new wells; recompletion, monitoring, and sampling of existing wells; well development and hydrologic/ aquifer testing; geophysical surveys; and subsidence crater recharge evaluation. Those wastes generated as a result of these activities will be managed in accordance with existing federal and state regulations, DOE Orders, and NNSA/NV waste minimization and pollution prevention objectives. This Waste Management Plan provides a general framework for all Underground Test Area (UGTA) Project participants to follow for the characterization, storage/accumulation, treatment, and disposal of wastes generated by UGTA Project activities. The objective of this waste management plan is to provide guidelines to minimize waste generation and to properly manage wastes that are produced. Attachment 1 to this plan is the Fluid Management Plan and details specific strategies for management of fluids produced under UGTA operations.

IT Corporation, Las Vegas

2002-04-24T23:59:59.000Z

239

U.S. PLANS AND STRATEGY FOR ITER BLANKET TESTING , M. Sawan4  

E-Print Network [OSTI]

U.S. PLANS AND STRATEGY FOR ITER BLANKET TESTING M. Abdou1 , D. Sze2 , C. Wong3 , M. Sawan4 , A. Ying1 , N. B. Morley1 , S. Malang5 1 UCLA Fusion Engineering Sciences, Los Angeles, CA, abdou

Abdou, Mohamed

240

Test plan for reactions between spent fuel and J-13 well water under unsaturated conditions  

SciTech Connect (OSTI)

The Yucca Mountain Site Characterization Project is evaluating the long-term performance of a high-level nuclear waste form, spent fuel from commercial reactors. Permanent disposal of the spent fuel is possible in a potential repository to be located in the volcanic tuff beds near Yucca Mountain, Nevada. During the post-containment period the spent fuel could be exposed to water condensation since of the cladding is assumed to fail during this time. Spent fuel leach (SFL) tests are designed to simulate and monitor the release of radionuclides from the spent fuel under this condition. This Test Plan addresses the anticipated conditions whereby spent fuel is contacted by small amounts of water that trickle through the spent fuel container. Two complentary test plans are presented, one to examine the reaction of spent fuel and J-13 well water under unsaturated conditions and the second to examine the reaction of unirradiated UO{sub 2} pellets and J-13 well water under unsaturated conditions. The former test plan examines the importance of the water content, the oxygen content as affected by radiolysis, the fuel burnup, fuel surface area, and temperature. The latter test plant examines the effect of the non-presence of Teflon in the test vessel.

Finn, P.A.; Wronkiewicz, D.J.; Hoh, J.C.; Emery, J.W.; Hafenrichter, L.D.; Bates, J.K.

1993-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "integrated test plan" 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

HEATER TEST PLANNING FOR THE NEAR SURFACE TEST FACILITY AT THE HANFORD RESERVATION  

E-Print Network [OSTI]

Heater Experiment at Hanford. Berkeley, Lawre ;e BerkeleyTest Facility, Hole DC-11, Hanford Reservation. Prepared forof Gable Mountain Basalt Cores, Hanford Nuclear Reservation.

DuBois, A.

2010-01-01T23:59:59.000Z

242

Pilot-scale treatability test plan for the 100-HR-3 operable unit  

SciTech Connect (OSTI)

This document presents the treatability test plan for pilot-scale pump-and-treat testing at the 100-HR-3 Operable Unit. The test will be conducted in fulfillment of interim Milestone M-15-06E to begin pilot-scale pump-and-treat operations by August 1994. The scope of the test was determined based on the results of lab/bench-scale tests (WHC 1993a) conducted in fulfillment of Milestone M-15-06B. These milestones were established per agreement between the U.S. Department of Energy (DOE), the Washington State Department of Ecology and the U.S. Environmental Protection Agency (EPA), and documented on Hanford Federal of Ecology Facility Agreement and Consent Order Change Control Form M-15-93-02. This test plan discusses a pilot-scale pump-and-treat test for the chromium plume associated with the D Reactor portion of the 100-HR-3 Operable Unit. Data will be collected during the pilot test to assess the effectiveness, operating parameters, and resource needs of the ion exchange (IX) pump-and-treat system. The test will provide information to assess the ability to remove contaminants by extracting groundwater from wells and treating extracted groundwater using IX. Bench-scale tests were conducted previously in which chromium VI was identified as the primary contaminant of concern in the 100-D reactor plume. The DOWEX 21K{trademark} resin was recommended for pilot-scale testing of an IX pump-and-treat system. The bench-scale test demonstrated that the system could remove chromium VI from groundwater to concentrations less than 50 ppb. The test also identified process parameters to monitor during pilot-scale testing. Water will be re-injected into the plume using wells outside the zone of influence and upgradient of the extraction well.

Not Available

1994-08-01T23:59:59.000Z

243

An approach to understanding, representing, and managing uncertainty in integrated resource planning  

SciTech Connect (OSTI)

This report addresses the issue of uncertainty in integrated resource planning (IRP). IRP is a process employed by electric utilities, often at the bellest of Public Utility Commissions (PUCs), to evaluate the acquisition of resources to meet forecast energy demands and other criteria such as energy efficiency and fuel diversity. Uncertainty plagues the preparation of IRPs, from forecasting energy prices and electricity demand to estimating costs and benefits expected from new resource acquisitions. As a result all those involved in the IRP process (including PUC commissioners and staff, utility decision makers, IRP analysts, and experts in particular areas) need to appreciate how uncertainty affects IRP and learn about available techniques to reduce its effects.

Tonn, B.E. [Oak Ridge National Lab., TN (United States); Schaffhauser, A.J. [Tennessee Univ., Knoxville, TN (United States)

1994-12-01T23:59:59.000Z

244

An integrated methodology for the specification, verification and testing of Professor Mike Holcombe,  

E-Print Network [OSTI]

testing issues are very rarely discussed by those involved in formal methods. This position is challenged and a mechanism is proposed whereby: testing is integrated more fully into the design process and, in particular to the extent of overcoming the traditional boundary between software and hardware design and testing methods

Holcombe, Mike

245

AN INTEGRATED TEST ENVIRONMENT FOR DISTRIBUTED APPLICATIONS HueyDer Chu and John E Dobson  

E-Print Network [OSTI]

1 AN INTEGRATED TEST ENVIRONMENT FOR DISTRIBUTED APPLICATIONS Huey­Der Chu and John E Dobson Centre ABSTRACT Software testing is an essential component in achieving software quality. However, it is a very, manual testing is unpopular and often inconsistently executed. Therefore, a powerful environment

Newcastle upon Tyne, University of

246

The 300 Area Integrated Field Research Challenge Quality Assurance Project Plan  

SciTech Connect (OSTI)

Pacific Northwest National Laboratory and a group of expert collaborators are using the U.S. Department of Energy Hanford Site 300 Area uranium plume within the footprint of the 300-FF-5 groundwater operable unit as a site for an Integrated Field-Scale Subsurface Research Challenge (IFRC). The IFRC is entitled Multi-Scale Mass Transfer Processes Controlling Natural Attenuation and Engineered Remediation: An IFRC Focused on the Hanford Site 300 Area Uranium Plume Project. The theme is investigation of multi-scale mass transfer processes. A series of forefront science questions on mass transfer are posed for research that relate to the effect of spatial heterogeneities; the importance of scale; coupled interactions between biogeochemical, hydrologic, and mass transfer processes; and measurements/approaches needed to characterize and model a mass transfer-dominated system. This Quality Assurance Project Plan provides the quality assurance requirements and processes that will be followed by the 300 Area IFRC Project. This plan is designed to be used exclusively by project staff.

Fix, N. J.

2009-04-29T23:59:59.000Z

247

Migrating data from TcSE to DOORS : an evaluation of the T-Plan Integrator software application.  

SciTech Connect (OSTI)

This report describes our evaluation of the T-Plan Integrator software application as it was used to transfer a real data set from the Teamcenter for Systems Engineering (TcSE) software application to the DOORS software application. The T-Plan Integrator was evaluated to determine if it would meet the needs of Sandia National Laboratories to migrate our existing data sets from TcSE to DOORS. This report presents the struggles of migrating data and focuses on how the Integrator can be used to map a data set and its data architecture from TcSE to DOORS. Finally, this report describes how the bulk of the migration can take place using the Integrator; however, about 20-30% of the data would need to be transferred from TcSE to DOORS manually. This report does not evaluate the transfer of data from DOORS to TcSE.

Post, Debra S. (Sandia National Laboratories, Livermore, CA); Manzanares, David A.; Taylor, Jeffrey L.

2011-02-01T23:59:59.000Z

248

Aircraft Integration and Flight Testing of 4STAR  

SciTech Connect (OSTI)

Under funding from the U.S. Dept. of Energy, in conjunction with a funded NASA 2008 ROSES proposal, with internal support from Battelle Pacific Northwest Division (PNWD), and in collaboration with NASA Ames Research Center, we successfully integrated the Spectrometer for Sky-Scanning, Sun-Tracking Atmospheric Research (4STAR-Air) instrument for flight operation aboard Battelle’s G-1 aircraft and conducted a series of airborne and ground-based intensive measurement campaigns (hereafter referred to as “intensives”) for the purpose of maturing the initial 4STAR-Ground prototype to a flight-ready science-ready configuration.

Flynn, CJ; Kassianov, E; Russell, P; Redemann, J; Dunagan, S; Holben, B

2012-10-12T23:59:59.000Z

249

Develop Standard Method of Test for Integrated Heat Pump  

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-UpHeat Pump Models |Conduct, Parent Company AgreesDesiree PipkinsSuperIntegrated Heat

250

Molten-Caustic-Leaching (MCL or Gravimelt) System Integration Project. Topical report for test circuit operation  

SciTech Connect (OSTI)

This is a report of the results obtained from the operation of an integrated test circuit for the Molten-Caustic-Leaching (MCL or Gravimelt) process for the desulfurization and demineralization of coal. The objectives of operational testing of the 20 pounds of coal per hour integrated MCL test circuit are: (1) to demonstrate the technical capability of the process for producing a demineralized and desulfurized coal that meets New Source Performance Standards (NSPS); (2) to determine the range of effective process operation; (3) to test process conditions aimed at significantly lower costs; and (4) to deliver product coal.

Not Available

1990-11-01T23:59:59.000Z

251

Evaluation of Packaging Film Mechanical Integrity Using a Standardized Scratch Test  

E-Print Network [OSTI]

EVALUATION OF PACKAGING FILM MECHANICAL INTEGRITY USING A STANDARDIZED SCRATCH TEST A Thesis by BRIAN ANTHONY HARE Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements... for the degree of MASTER OF SCIENCE August 2011 Major Subject: Materials Science and Engineering Evaluation of Packaging Film Mechanical Integrity Using a Standardized Scratch Test Copyright 2011 Brian...

Hare, Brian

2012-10-19T23:59:59.000Z

252

Evaluation of Integrated High Temperature Component Testing Needs  

SciTech Connect (OSTI)

This paper describes the requirements for a large-scale component test capability to support the development of advanced nuclear reactor technology and their adaptation to commercial applications that advance U.S. energy economy, reliability, and security and reduce carbon emissions.

Rafael Soto; David Duncan; Vincent Tonc

2009-05-01T23:59:59.000Z

253

Utility Integrated Resource Planning: An Emerging Driver of New Renewable Generation in the Western United States  

E-Print Network [OSTI]

towards that portfolio. Renewable resources were once rarelyobjectively evaluate renewable resources. Planned Renewableamount of planned renewable resource additions. In the case

Bolinger, Mark; Wiser, Ryan

2005-01-01T23:59:59.000Z

254

Adaptive Management Plan for Sensitive Plant Species on the Nevada Test Site  

SciTech Connect (OSTI)

The Nevada Test Site supports numerous plant species considered sensitive because of their past or present status under the Endangered Species Act and with federal and state agencies. In 1998, the U.S. Department of Energy, Nevada Operation Office (DOE/NV) prepared a Resource Management Plan which commits to protects and conserve these sensitive plant species and to minimize accumulative impacts to them. This document presents the procedures of a long-term adaptive management plan which is meant to ensure that these goals are met. It identifies the parameters that are measured for all sensitive plant populations during long-term monitoring and the adaptive management actions which may be taken if significant threats to these populations are detected. This plan does not, however, identify the current list of sensitive plant species know to occur on the Nevada Test Site. The current species list and progress on their monitoring is reported annually by DOE/NV in the Resource Management Plan.

C. A. Wills

2001-03-01T23:59:59.000Z

255

ENERGY SMART SCHOOLS APPLIED RESEARCH, FIELD TESTING, AND TECHNOLOGY INTEGRATION  

SciTech Connect (OSTI)

This multi-state collaborative project brings together federal, state, and private sector resources in order to move the design and use of high-performance energy technologies in schools to the forefront. NASEO and its contractors continue to make progress on completion of the statement of work. The high watermark for this period is the installation and operation of the micro-turbine in the Canton School District. The school is pleased to begin the monitoring phase of the project and looks forward to a ribbon cutting this Spring. The other projects continue to move forward and NYSERDA has now begun work in earnest. We expect the NASEO/NYSERDA workshop sometime this Spring as well. By the time the next Annual Technical Progress Report is submitted, we plan to have finished all of the work. The next year should be filled with dissemination of information to interested parties on the success of the project in an effort to get others to duplicate the high performance, and energy smart schools initiatives. We expect all of the deliverables to be completed with the possible exception of the high-performance schools retrofits in California. We expect that 2 of the 3 campuses undergoing retrofits will be complete and the third will be nearly complete. All other activities are on schedule for 10/1/03 completion at this time.

Frank Bishop

2003-04-01T23:59:59.000Z

256

Applying Retirement-Planning Strategy to Sensor Networks: An Integrated Approach to Energy-Aware Medium Access  

E-Print Network [OSTI]

lifetime, energy efficiency, cross-layer design. #12;TECHNICAL REPORT TR-06-01, UC DAVIS, MAY 2006. 2 I among #12;TECHNICAL REPORT TR-06-01, UC DAVIS, MAY 2006. 3 nodes. We show that protocols exploitingApplying Retirement-Planning Strategy to Sensor Networks: An Integrated Approach to Energy

Islam, M. Saif

257

Overseas Affairs and Planning Institute for Integrated Cell-Material Sciences (iCeMS), Kyoto University  

E-Print Network [OSTI]

Contact: Overseas Affairs and Planning Institute for Integrated Cell-Material Sciences (i Cell-Material Sciences, iCeMS for short, I welcome you to the Seventh iCeMS International Symposium to develop them through evolution. They are also very important to design and create various novel "smart

Takada, Shoji

258

A Process Model of Applicant Faking on Overt Integrity Tests  

E-Print Network [OSTI]

of empirically tested models or appropriate theoretical structures to explain the process (Griffith & McDaniel, 2006; Murphy, 2000). Moreover, there seems to be a limited understanding of possible outcomes associated with applicant faking..., Barrett, & Hogan, 2007; McFarland & Ryan, 2006; Morgeson et al., 2007). According to recent studies, approximately 30-50% of job applicants consciously try to elevate their scores (Donovan, Dwight, & Hurtz, 2003; Griffith et al., 2007)1. Faking...

Yu, Janie

2010-01-14T23:59:59.000Z

259

Test plan: Laboratory-scale testing of the first core sample from Tank 102-AZ  

SciTech Connect (OSTI)

The overall objectives of the Radioactive Process/Product Laboratory Testing (RPPLT), WBS 1.2.2.05.05, are to confirm that simulated HWVP feed and glass are representative of actual radioactive HWVP feed and glass and to provide radioactive leaching and glass composition data to WFQ. This study will provide data from one additional NCAW core sample (102-AZ Core 1) for these purposes.

Morrey, E.V.

1996-03-01T23:59:59.000Z

260

Convergence and divergence testing theory and applications by Integration at a point  

E-Print Network [OSTI]

Integration at a point is a new kind of integration derived from integration over an interval in infinitesimal and infinity domains which are spaces larger than the reals. Consider a continuous monotonic divergent function that is continually increasing. Apply the fundamental theorem of calculus. The integral is a difference of the function integrated at the end points. If one of these point integrals is much-greater-than the other in magnitude delete it by non-reversible arithmetic. We call this type of integration "convergence sums" because our primary application is a theory for the determination of convergence and divergence of sums and integrals. The theory is far-reaching. It reforms known convergence tests and arrangement theorems, and it connects integration and series switching between the different forms. By separating the finite and infinite domains, the mathematics is more naturally considered, and is a problem reduction. In this endeavour we rediscover and reform the "boundary test" which we believe to be the boundary between convergence and divergence: the boundary is represented as an infinite class of generalized p-series functions. All this is derived from extending du Bois-Reymond's theory with gossamer numbers and function comparison algebra.

Chelton D. Evans; William K. Pattinson

2015-03-03T23:59:59.000Z

Note: This page contains sample records for the topic "integrated test plan" 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

CoalFleet RD&D augmentation plan for integrated gasification combined cycle (IGCC) power plants  

SciTech Connect (OSTI)

To help accelerate the development, demonstration, and market introduction of integrated gasification combined cycle (IGCC) and other clean coal technologies, EPRI formed the CoalFleet for Tomorrow initiative, which facilitates collaborative research by more than 50 organizations from around the world representing power generators, equipment suppliers and engineering design and construction firms, the U.S. Department of Energy, and others. This group advised EPRI as it evaluated more than 120 coal-gasification-related research projects worldwide to identify gaps or critical-path activities where additional resources and expertise could hasten the market introduction of IGCC advances. The resulting 'IGCC RD&D Augmentation Plan' describes such opportunities and how they could be addressed, for both IGCC plants to be built in the near term (by 2012-15) and over the longer term (2015-25), when demand for new electric generating capacity is expected to soar. For the near term, EPRI recommends 19 projects that could reduce the levelized cost-of-electricity for IGCC to the level of today's conventional pulverized-coal power plants with supercritical steam conditions and state-of-the-art environmental controls. For the long term, EPRI's recommended projects could reduce the levelized cost of an IGCC plant capturing 90% of the CO{sub 2} produced from the carbon in coal (for safe storage away from the atmosphere) to the level of today's IGCC plants without CO{sub 2} capture. EPRI's CoalFleet for Tomorrow program is also preparing a companion RD&D augmentation plan for advanced-combustion-based (i.e., non-gasification) clean coal technologies (Report 1013221). 7 refs., 30 figs., 29 tabs., 4 apps.

NONE

2007-01-15T23:59:59.000Z

262

A hybrid electron and photon IMRT planning technique that lowers normal tissue integral patient dose using standard hardware  

SciTech Connect (OSTI)

Purpose: To present a mixed electron and photon IMRT planning technique using electron beams with an energy range of 6-22 MeV and standard hardware that minimizes integral dose to patients for targets as deep as 7.5 cm. Methods: Ten brain cases, two lung, a thyroid, an abdominal, and a parotid case were planned using two planning techniques: a photon-only IMRT (IMRT) versus a mixed modality treatment (E + IMRT) that includes an enface electron beam and a photon IMRT portion that ensures a uniform target coverage. The electron beam is delivered using a regular cutout placed in an electron cone. The electron energy was chosen to provide a good trade-off between minimizing integral dose and generating a uniform, deliverable plan. The authors choose electron energies that cover the deepest part of PTV with the 65%-70% isodose line. The normal tissue integral dose, the dose for ring structures around the PTV, and the volumes of the 75%, 50%, and 25% isosurfaces were used to compare the dose distributions generated by the two planning techniques. Results: The normal tissue integral dose was lowered by about 20% by the E + IMRT plans compared to the photon-only IMRT ones for most studied cases. With the exception of lungs, the dose reduction associated to the E + IMRT plans was more pronounced further away from the target. The average dose ratio delivered to the 0-2 cm and the 2-4 cm ring structures for brain patients for the two planning techniques were 89.6% and 70.8%, respectively. The enhanced dose sparing away from the target for the brain patients can also be observed in the ratio of the 75%, 50%, and 25% isodose line volumes for the two techniques, which decreases from 85.5% to 72.6% and further to 65.1%, respectively. For lungs, the lateral electron beams used in the E + IMRT plans were perpendicular to the mostly anterior/posterior photon beams, generating much more conformal plans. Conclusions: The authors proved that even using the existing electron delivery hardware, a mixed electron/photon planning technique (E + IMRT) can decrease the normal tissue integral dose compared to a photon-only IMRT plan. Different planning approaches can be enabled by the use of an electron beam directed toward organs at risk distal to the target, which are still spared due the rapid dose fall-off of the electron beam. Examples of such cases are the lateral electron beams in the thoracic region that do not irradiate the heart and contralateral lung, electron beams pointed toward kidneys in the abdominal region, or beams treating brain lesions pointed toward the brainstem or optical apparatus. For brain, electron vertex beams can also be used without irradiating the whole body. Since radiation retreatments become more and more common, minimizing the normal tissue integral dose and the dose delivered to tissues surrounding the target, as enabled by E + IMRT type techniques, should receive more attention.

Rosca, Florin [Department of Radiation Oncology, Massachusetts General Hospital, Danvers, Massachusetts 01923 (United States)

2012-06-15T23:59:59.000Z

263

Integrating knowledge-based techniques into well-test interpretation  

SciTech Connect (OSTI)

The goal of the Spirit Project was to develop a prototype of next-generation well-test-interpretation (WTI) software that would include knowledge-based decision support for the WTI model selection task. This paper describes how Spirit makes use of several different types of information (pressure, seismic, petrophysical, geological, and engineering) to support the user in identifying the most appropriate WTI model. Spirit`s knowledge-based approach to type-curve matching is to generate several different feasible interpretations by making assumptions about the possible presence of both wellbore storage and late-time boundary effects. Spirit fuses information from type-curve matching and other data sources by use of a knowledge-based decision model developed in collaboration with a WTI expert. The sponsors of the work have judged the resulting prototype system a success.

Harrison, I.W.; Fraser, J.L. [Artificial Intelligence Applications Inst., Edinburgh (United Kingdom)

1995-04-01T23:59:59.000Z

264

SWEPP Assay System Version 2.0 software test plan and report  

SciTech Connect (OSTI)

The Idaho National Engineering Laboratory (INEL) Stored Waste Examination Pilot Plant (SWEPP) operations staff use nondestructive analysis methods to characterize the radiological contents of contact- handled waste containers. Containers of waste from Rocky Flats Environmental Technology Site and other DOE sites are currently stored at SWEPP. Before these containers can be shipped to the Waste Isolation Pilot Plant (WIPP), SWEPP must verify compliance with storage, shipping, and disposal requirements. One part of the SWEPP program measures neutron emissions from the containers and estimates the mass of plutonium and other transuranic (TRU) isotopes present. A Passive/Active Neutron (PAN) assay system developed at the Los Alamos National Laboratory is used to perform these measurements. A computer program named NEUT2 was used to perform the data acquisition and reduction functions for the neutron measurements. NEUT2 uses the analysis methodology outlined, but no formal documentation exists on the software itself The SWEPP Assay System (SAS) computer program replaced the NEUT2 software. The SAS software was developed using an `object model` approach. The new software incorporates the basic analysis algorithms found in NEUT2. Additional improvements include an improved user interface, the ability to change analysis parameters without having to modify the code, and other features for maintainability. The primary purpose of this test plan and report is to document the test process and to verify that the requirements for the SAS are implemented correctly. This test plan and report satisfies the testing requirements of ASME NQA-1-1994 Supplement 11S-2 for a Quality Level 2 application. The intended audiences for this test plan are the developers and verification and validation analysts for the SAS.

Ferguson, J.J.; Overlin, T.K.

1996-07-01T23:59:59.000Z

265

AFCI Fuel Irradiation Test Plan, Test Specimens AFC-1Æ and AFC-1F  

SciTech Connect (OSTI)

The U. S. Advanced Fuel Cycle Initiative (AFCI) seeks to develop and demonstrate the technologies needed to transmute the long-lived transuranic actinide isotopes contained in spent nuclear fuel into shorter-lived fission products, thereby dramatically decreasing the volume of material requiring disposition and the long-term radiotoxicity and heat load of high-level waste sent to a geologic repository (DOE, 2003). One important component of the technology development is actinide-bearing transmutation fuel forms containing plutonium, neptunium, americium (and possibly curium) isotopes. There are little irradiation performance data available on non-fertile fuel forms, which would maximize the destruction rate of plutonium, and low-fertile (i.e., uranium-bearing) fuel forms, which would support a sustainable nuclear energy option. Initial scoping level irradiation tests on a variety of candidate fuel forms are needed to establish a transmutation fuel form design and evaluate deployment of transmutation fuels.

D. C. Crawford; S. L. Hayes; B. A. Hilton; M. K. Meyer; R. G. Ambrosek; G. S. Chang; D. J. Utterbeck

2003-11-01T23:59:59.000Z

266

Test Plan for Characterization Testing of SO2-depolarized Electrolyzer Cell Designs  

SciTech Connect (OSTI)

SRNL received funding in FY 2005 to test the Hybrid Sulfur (HyS) Process for generating hydrogen. This technology employs an electrolyzer that uses a sulfur dioxide depolarized anode to greatly reduce the electrical energy requirement. The required current is the same as for conventional electrolysis of water, but the required cell voltage is reduced. The electrolyzer is a key part of HyS technology. Completing the material loop for HyS requires a high temperature decomposition of sulfuric acid to regenerate the sulfur dioxide gas needed for the anode reaction. Oxygen is also produced and could be sold. The decomposition of sulfuric acid is being studied by others in a separately funded task. It is not included in this SRNL task.

Steimke, J. L.

2006-02-15T23:59:59.000Z

267

RERTR Program: goals, progress and plans. [Reduced Enrichment Research and Test Reactor  

SciTech Connect (OSTI)

The status of the US Reduced Enrichment Research and Test Reactor (RERTR) Program is reviewed. After a brief outline of RERTR Program objectives and goals, program accomplishments are discussed with emphasis on the development, demonstration and application of new LEU fuels. Most program activities have proceeded as planned, and a combination of two silicide fuels (U/sub 3/Si/sub 2/-Al and U/sub 3/Si-Al) holds excellent promise for achieving the long-term program goals. Current plans and schedules project the uranium density of qualified RERTR fuels for plate-type reactors to grow by approximately 1 g U/cm/sup 3/ each year, from the nearly null value of 1982 to the 7.0 g U/cm/sup 3/ which will be reached in early 1989. The technical needs of research reactors for HEU exports are also estimated to undergo a gradual but dramatic decline in the coming years.

Travelli, A.

1984-09-25T23:59:59.000Z

268

Test Plan to Evaluate the Relationship Among IAQ, Comfort, Moisture, and Ventilation in Humid Climates  

SciTech Connect (OSTI)

This experimental plan describes research being conducted by Pacific Northwest National Laboratory (PNNL), in coordinatation with Florida Solar Energy Center (FSEC), Florida HERO, and Lawrence Berkeley National Laboratory (LBNL) to evaluate the impact of ventilation rate on interior moisture levels, temperature distributions, and indoor air contaminant concentrations. Specifically, the research team will measure concentrations of indoor air contaminants, ventilation system flow rates, energy consumption, and temperature and relative humidity in ten homes in Gainesville, FL to characterize indoor pollutant levels and energy consumption associated with the observed ventilation rates. PNNL and FSEC have collaboratively prepared this experimental test plan, which describes background and context for the proposed study; the experimental design; specific monitoring points, including monitoring equipment, and sampling frequency; key research questions and the associated data analysis approach; experimental logistics, including schedule, milestones, and team member contact information; and clearly identifies the roles and responsibilities of each team in support of project objectives.

Widder, Sarah H.; Martin, Eric

2013-03-15T23:59:59.000Z

269

Fluid Management Plan Central Nevada Test Area Corrective Action Unit 443  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office initiated the Offsites Project to characterize the risk posed to human health and the environment as a result of underground nuclear testing at sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. Responsibility for environmental restoration of the sites that constitute the Offsites Project was transferred from the DOE Office of Environmental Management to the DOE Office of Legacy Management (LM) on October 1, 2006. The scope of this Fluid Management Plan (FMP) is to support subsurface investigations at the Central Nevada Test Area (CNTA) Corrective Action Unit (CAU) 443, in accordance with the Federal Facility Agreement and Consent Order (FFACO) (1996). The subsurface CAU 443 is associated with the underground nuclear testing conducted at UC-1 and is located approximately 30 miles north of Warm Springs in Nye County, Nevada.

None

2009-01-01T23:59:59.000Z

270

Status and Plans for an SRF Accelerator Test Facility at Fermilab  

E-Print Network [OSTI]

A superconducting RF accelerator test facility is currently under construction at Fermilab. The accelerator will consist of an electron gun, 40 MeV injector, beam acceleration section consisting of 3 TTF-type or ILC-type cryomodules, and multiple downstream beam lines for testing diagnostics and performing beam experiments. With 3 cryomodules installed this facility will initially be capable of generating an 810 MeV electron beam with ILC beam intensity. The facility can accommodate up to 6 cryomodules for a total beam energy of 1.5 GeV. This facility will be used to test SRF cryomodules under high intensity beam conditions, RF power equipment, instrumentation, and LLRF and controls systems for future SRF accelerators such as the ILC and Project-X. This paper describes the current status and overall plans for this facility.

Church, M; Nagaitsev, S

2012-01-01T23:59:59.000Z

271

Quality Assurance Program Plan for TRUPACT-II Gas Generation Test Program  

SciTech Connect (OSTI)

The Gas Generation Test Program (GGTP), referred to as the Program, is designed to establish the concentration of flammable gases and/or gas generation rates in a test category waste container intended for shipment in the Transuranic Package Transporter-II (TRUPACT-II). The phrase "gas generationtesting" shall refer to any activity that establishes the flammable gas concentration or the flammable gas generation rate. This includes, but is not limited to, measurements performed directly on waste containers or during tests performed on waste containers. This Quality Assurance Program Plan (QAPP) documents the quality assurance (QA) and quality control (QC) requirements that apply to the Program. The TRUPACT-II requirements and technical bases for allowable flammable gas concentration and gas generation rates are described in the TRUPACT-II Authorized Methods for Payload Control (TRAMPAC).

Carlsbad Field Office

2002-03-01T23:59:59.000Z

272

Test Planning for Mixed-Signal SOCs with Wrapped Analog Cores Anuja Sehgal, Fang Liu, Sule Ozev and Krishnendu Chakrabarty  

E-Print Network [OSTI]

Test Planning for Mixed-Signal SOCs with Wrapped Analog Cores Anuja Sehgal, Fang Liu, Sule Ozev. Even though the test cost for such mixed-signal SOCs is significantly higher than that for digital SOCs, most prior research in this area has focused exclusively on digital cores. We propose a low-cost test

Paris-Sud XI, Université de

273

Joint Test Plan to Identify the Gaseous By-Products of CH3I Loading on AgZ  

SciTech Connect (OSTI)

The objective of this test plan is to describe research to determine the gaseous by-products of the adsorption of CH3I on hydrogen reduced silver exchanged mordenite (AgZ).

R. T. Jubin; N. R. Soelberg; D. M. Strachan; T. M. Nenoff; B. B. Spencer

2012-12-01T23:59:59.000Z

274

warned that the world was asleep at the wheel. Back then, only two countries had plans to test  

E-Print Network [OSTI]

warned that the world was asleep at the wheel. Back then, only two countries had plans to test in a hospital examin- ing room in Rochester, New York. Pressing a ball of cotton into the crook of her elbow

Cai, Long

275

Test plan for long-term, low-temperature oxidation of BWR spent fuel  

SciTech Connect (OSTI)

Preliminary studies indicated the need for more spent fuel oxidation data in order to determine the probable behavior of spent fuel in a tuff repository. Long-term, low-temperature testing was recommended in a comprehensive technical approach to (1) confirm the findings of the short-term thermogravimetric analysis tests; (2) evaluate the effects of variables such as burnup, atmospheric moisture,and fuel type on the oxidation rate; and (3) extend the oxidation data base to representative repository temperatures and better define the temperature dependence of the operative oxidation mechanisms. This document presents the test plan to study the effects of atmospheric moisture and temperature on oxidation rate and phase formation using a large number of boiling-water reactor fuel samples. Tests will run for up to two years, use characterized fragmented and pulverized fuel samples, cover a temperature range of 110{degree}C to 175{degree}C, and be conducted with an atmospheric moisture content ranging from <{minus}55{degree}C to {approximately}80{degree}C dew point. After testing, the samples will be examined and made available for leaching testing. 15 refs., 2 figs., 2 tabs.

Einziger, R.E.

1988-12-01T23:59:59.000Z

276

Phase II test plan for the evaluation of the performance of container filling systems  

SciTech Connect (OSTI)

The PHMC will provide tank wastes for final treatment by BNFL from Hanford's waste tanks. Concerns about the ability for ''grab'' sampling to provide large volumes of representative waste samples has led to the development of a nested, fixed-depth sampling system. Preferred concepts for filling sample containers that meet RCRA organic sample criteria were identified by a PHMC Decision Board. These systems will replace the needle based sampling ''T'' that is currently on the sampling system. This test plan document identifies cold tests with simulants that will demonstrate the preferred bottle filling concepts abilities to provide representative waste samples and will meet RCRA criteria. Additional tests are identified that evaluate the potential for cross-contamination between samples and the ability for the system to decontaminate surfaces which have contacted tank wastes. These tests will be performed with kaolid/water and sand/water slurry simulants in the test rig that was used by AEAT to complete Phase 1 tests in FY 1999.

BOGER, R.M.

1999-09-28T23:59:59.000Z

277

New York City Energy-Water Integrated Planning: A Pilot Study  

SciTech Connect (OSTI)

The New York City Energy-Water Integrated Planning Pilot Study is one of several projects funded by Sandia National Laboratories under the U.S. Department of Energy Energy-Water Nexus Program. These projects are intended to clarify some key issues and research needs identified during the Energy-Water Nexus Roadmapping activities. The objectives of the New York City Pilot Project are twofold: to identify energy-water nexus issues in an established urban area in conjunction with a group of key stakeholders and to define and apply an integrated energy and water decision support tool, as proof-of-concept, to one or more of these issues. During the course of this study, the Brookhaven National Laboratory project team worked very closely with members of a Pilot Project Steering Committee. The Steering Committee members brought a breadth of experience across the energy, water and climate disciplines, and all are well versed in the particular issues faced by an urban environment, and by New York City in particular. The first task was to identify energy-water issues of importance to New York City. This exercise was followed by discussion of the qualities and capabilities that an ideal decision support tool should display to address these issues. The decision was made to start with an existing energy model, the New York City version of the MARKAL model, developed originally at BNL and now used globally by many groups for energy analysis. MARKAL has the virtue of being well-vetted, transparent, and capable of calculating 'material' flows, such as water use by the energy system and energy requirements of water technology. The Steering Committee members defined five scenarios of interest, representing a broad spectrum of New York City energy-water issues. Brookhaven National Laboratory researchers developed a model framework (Water-MARKAL) at the desired level of detail to address the scenarios, and then attempted to gather the New York City-specific information required to analyze the scenarios using Water-MARKAL. This report describes the successes and challenges of defining and demonstrating the decision tool, Water-MARKAL. The issues that the stakeholders perceive for New York City are listed and the difficulties in gathering required information for Water-MARKAL to analyze these issues at the desired level of detail are described.

Bhatt,V.; Crosson, K. M.; Horak, W.; Reisman, A.

2008-12-16T23:59:59.000Z

278

HWMA/RCRA CLOSURE PLAN FOR THE MATERIALS TEST REACTOR WING (TRA-604) LABORATORY COMPONENTS VOLUNTARY CONSENT ORDER ACTION PLAN VCO-5.8 D REVISION2  

SciTech Connect (OSTI)

This Hazardous Waste Management Act/Resource Conservation and Recovery Act closure plan was developed for the laboratory components of the Test Reactor Area Catch Tank System (TRA-630) that are located in the Materials Test Reactor Wing (TRA-604) at the Reactor Technology Complex, Idaho National Laboratory Site, to meet a further milestone established under Voluntary Consent Order Action Plan VCO-5.8.d. The TRA-604 laboratory components addressed in this closure plan were deferred from the TRA-630 Catch Tank System closure plan due to ongoing laboratory operations in the areas requiring closure actions. The TRA-604 laboratory components include the TRA-604 laboratory warm wastewater drain piping, undersink drains, subheaders, and the east TRA-604 laboratory drain header. Potentially contaminated surfaces located beneath the TRA-604 laboratory warm wastewater drain piping and beneath the island sinks located in Laboratories 126 and 128 (located in TRA-661) are also addressed in this closure plan. The TRA-604 laboratory components will be closed in accordance with the interim status requirements of the Hazardous Waste Management Act/Resource Conservation and Recovery Act as implemented by the Idaho Administrative Procedures Act 58.01.05.009 and 40 Code of Federal Regulations 265, Subparts G and J. This closure plan presents the closure performance standards and the methods for achieving those standards.

KIRK WINTERHOLLER

2008-02-25T23:59:59.000Z

279

Design methodologies for built-in testing of integrated RF transceivers with the on-chip loopback technique  

E-Print Network [OSTI]

Advances toward increased integration and complexity of radio frequency (RF) andmixed-signal integrated circuits reduce the effectiveness of contemporary testmethodologies and result in a rising cost of testing. The focus in this research...

Onabajo, Marvin Olufemi

2009-05-15T23:59:59.000Z

280

Dual Axis Radiographic Hydrodynamic Test Facility mitigation action plan. Annual report for 1997  

SciTech Connect (OSTI)

This Mitigation Action Plan Annual Report (MAPAR) has been prepared by the US Department of Energy (DOE) as part of implementing the Dual Axis Radiographic Hydrodynamic Test Facility (DARHT) Mitigation Action Plan (MAP). This MAPAR provides a status on specific DARHT facility design- and construction-related mitigation actions that have been initiated in order to fulfill DOE`s commitments under the DARHT MAP. The functions of the DARHT MAP are to (1) document potentially adverse environmental impacts of the Phased Containment Option delineated in the Final EIS, (2) identify commitments made in the Final EIS and ROD to mitigate those potential impacts, and (3) establish Action Plans to carry out each commitment (DOE 1996). The DARHT MAP is divided into eight sections. Sections 1--5 provide background information regarding the NEPA review of the DARHT project and an introduction to the associated MAP. Section 6 references the Mitigation Action Summary Table which summaries the potential impacts and mitigation measures; indicates whether the mitigation is design-, construction-, or operational-related; the organization responsible for the mitigation measure; and the projected or actual completion data for each mitigation measure. Sections 7 and 8 discuss the Mitigation Action Plan Annual Report and Tracking System commitment and the Potential Impacts, Commitments, and Action Plans respectively. Under Section 8, potential impacts are categorized into five areas of concern: General Environment, including impacts to air and water; Soils, especially impacts affecting soil loss and contamination; Biotic Resources, especially impacts affecting threatened and endangered species; Cultural/Paleontological Resources, especially impacts affecting the archeological site known as Nake`muu; and Human Health and Safety, especially impacts pertaining to noise and radiation. Each potential impact includes a brief statement of the nature of the impact and its cause(s). The commitment made to mitigate the potential impact is identified and the Action Plan for each commitment is described in detail, with a description of actions to be taken, pertinent time frames for the actions, verification of mitigation activities, and identification of agencies/organizations responsible for satisfying the requirements of the commitment.

Haagenstad, H.T.

1998-01-15T23:59:59.000Z

Note: This page contains sample records for the topic "integrated test plan" 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

Advanced sluicing system test report for single shell tank waste retrieval integrated testing  

SciTech Connect (OSTI)

This document describes the testing performed by ARD Environmental, Inc., and Los Alamos Technical Associates of the LATA/ARD Advanced Sluicing System, in support of ACTR Phase 1 activities. Testing was to measure the impact force and pressures of sluicing streams at three different distances, as measured by the Government supplied load cell. Simulated sluicing of large simulated salt cake and hard pan waste coupons was also performed. Due to operational difficulties experienced with the Government supplied load cell, no meaningful results with respect to sluice stream impact pressure distribution or stream coherence were obtained. Sluice testing using 3000 psi salt cake simulants measured waste retrieval rates of approximately 12 Ml/day (17.6 ft{sup 3}/hr). Rates as high as 314 m{sup 3}/day (463 ft{sup 3}/hr) were measured against the lower strength salt cake simulants.

Berglin, E.J.

1997-05-29T23:59:59.000Z

282

Acid rain program: CEMS submission instructions for monitoring plans, certification test notifications, and quarterly reports  

SciTech Connect (OSTI)

The Acid Rain Program regulations require all affected utility units to continuously measure, record and report SO2, NOx, volumetric flow data and CO2 emissions. All affected units also must continuously measure and record opacity, and must report opacity exceedances to the appropriate State or Local Agency. To ensure that your CEMS and fuel flowmeters are performing at an acceptable level, and providing quality assured data, you are required under 40 CFR 75.53, 75.62 (a) to submit a monitoring plan and certification test data for acid rain CEM certificaton. The purpose of this handbook is to help you fulfill your requirements under the Acid Rain Program. This handbook will walk you through the necessary steps for gaining CEMS certification, including filling out and mailing the proper forms, administering the required tests, and applying for certification and sending in electronic data to EPA.

NONE

1995-05-12T23:59:59.000Z

283

Tank 241-AZ-101 Mixer Pump Test Vapor Sampling and Analysis Plan  

SciTech Connect (OSTI)

This sampling and analysis plan (SAP) identifies characterization objectives pertaining to sample collection, laboratory analytical evaluation, and reporting requirements for vapor samples obtained during the operation of mixer pumps in tank 241-AZ-101. The primary purpose of the mixer pump test (MPT) is to demonstrate that the two 300 horsepower mixer pumps installed in tank 241-AZ-101 can mobilize the settled sludge so that it can be retrieved for treatment and vitrification Sampling will be performed in accordance with Tank 241-AZ-101 Mixer Pump Test Data Quality Objective (Banning 1999) and Data Quality Objectives for Regulatory Requirements for Hazardous and Radioactive Air Emissions Sampling and Analysis (Mulkey 1999). The sampling will verify if current air emission estimates used in the permit application are correct and provide information for future air permit applications.

TEMPLETON, A.M.

2000-01-31T23:59:59.000Z

284

Utility Integrated Resource Planning: An Emerging Driver of New Renewable Generation in the Western United States  

E-Print Network [OSTI]

in their treatment of renewable resources and the costs andtowards that portfolio. Renewable resources were once rarelyobjectively evaluate renewable resources. Planned Renewable

Bolinger, Mark; Wiser, Ryan

2005-01-01T23:59:59.000Z

285

Supplemental Investigation Plan for FFACO Use Restrictions, Nevada Test Site, Nevada, Revision 0  

SciTech Connect (OSTI)

This document is part of an effort to re-evaluate all FFACO URs against the current RBCA criteria (referred to in this document as the Industrial Sites [IS] RBCA process) as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006a). After reviewing all of the existing FFACO URs, the 12 URs addressed in this Supplemental Investigation Plan (SIP) could not be evaluated against the current RBCA criteria as sufficient information about the contamination at each site was not available. This document presents the plan for conducting field investigations to obtain the needed information. This SIP includes URs from Corrective Action Units (CAUs) 326, 339, 358, 452, 454, 464, and 1010, located in Areas 2, 6, 12, 19, 25, and 29 of the Nevada Test Site, which is approximately 65 miles northwest of Las Vegas, Nevada; and CAU 403, located in Area 3 of the Tonopah Test Range, which is approximately 165 miles north of Las Vegas, Nevada.

Lynn Kidman

2008-02-01T23:59:59.000Z

286

NREL Vehicle Testing and Integration Facility (VTIF): Rotating Shadowband Radiometer (RSR); Golden, Colorado (Data)  

DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

This measurement station at NREL's Vehicle Testing and Integration Facility (VTIF) monitors global horizontal, direct normal, and diffuse horizontal irradiance to define the amount of solar energy that hits this particular location. The solar measurement instrumentation is also accompanied by meteorological monitoring equipment.

Lustbader, J.; Andreas, A.

287

Fusion Engineering and Design 7579 (2005) 2932 First integrated test of the superconducting magnet systems  

E-Print Network [OSTI]

Fusion Engineering and Design 75­79 (2005) 29­32 First integrated test of the superconducting of Applied Physics and Applied Mathematics Room 210 S.W., Mudd Building, New York, NY 10027, USA Available at the center of a 5 m diameter, 3 m tall vacuum chamber. The Floating coil (F-coil) is designed for a maximum

288

Corrective action investigation plan for Central Nevada Test Area, CAU No. 417  

SciTech Connect (OSTI)

This Corrective Action Investigation Plan (CAIP) is part of a US Department of Energy (DOE)-funded environmental investigation of the Central Nevada Test Area (CNTA). This CAIP addresses the surface investigation and characterization of 15 identified Corrective Action Sites (CASs). In addition, several other areas of the CNTA project area have surface expressions that may warrant investigation. These suspect areas will be characterized, if necessary, in subsequent CAIPs or addendums to this CAIP prepared to address these sites. This CAIP addresses only the 15 identified CASs as shown in Table 2-1 that are associated with the drilling and construction of a number of testing wells designed as part of an underground nuclear testing program. The purpose of the wells at the time of construction was to provide subsurface access for the emplacement, testing, and post detonation evaluations of underground nuclear devices. If contamination is found at any of the 15-surface CASs, the extent of contamination will be determined in order to develop an appropriate corrective action.

NONE

1997-04-01T23:59:59.000Z

289

Integrated DWPF Melter System (IDMS) campaign report: Hanford Waste Vitrification Plan (HWVP) process demonstration  

SciTech Connect (OSTI)

Vitrification facilities are being developed worldwide to convert high-level nuclear waste to a durable glass form for permanent disposal. Facilities in the United States include the Department of Energy`s Defense Waste Processing Facility (DWPF) at the Savannah River Site, the Hanford Waste Vitrification Plant (HWVP) at the Hanford Site and the West Valley Demonstration Project (WVDP) at West Valley, NY. At each of these sites, highly radioactive defense waste will be vitrified to a stable borosilicate glass. The DWPF and WVDP are near physical completion while the HWVP is in the design phase. The Integrated DWPF Melter System (IDMS) is a vitrification test facility at the Savannah River Technology Center (SRTC). It was designed and constructed to provide an engineering-scale representation of the DWPF melter and its associated feed preparation and off-gas treatment systems. Because of the similarities of the DWPF and HWVP processes, the IDMS facility has also been used to characterize the processing behavior of a reference NCAW simulant. The demonstration was undertaken specifically to determine material balances, to characterize the evolution of offgas products (especially hydrogen), to determine the effects of noble metals, and to obtain general HWVP design data. The campaign was conducted from November, 1991 to February, 1992.

Hutson, N.D.

1992-08-10T23:59:59.000Z

290

Cold test plan for the Old Hydrofracture Facility tank contents removal project, Oak Ridge National Laboratory, Oak Ridge, Tennessee  

SciTech Connect (OSTI)

This Old Hydrofracture Facility (OHF) Tanks Contents Removal Project Cold Test Plan describes the activities to be conducted during the cold test of the OHF sluicing and pumping system at the Tank Technology Cold Test Facility (TTCTF). The TTCTF is located at the Robotics and Process Systems Complex at the Oak Ridge National Laboratory (ORNL). The cold test will demonstrate performance of the pumping and sluicing system, fine-tune operating instructions, and train the personnel in the actual work to be performed. After completion of the cold test a Technical Memorandum will be prepared documenting completion of the cold test, and the equipment will be relocated to the OHF site.

NONE

1997-11-01T23:59:59.000Z

291

DNFSB Recommendation 94-1 Hanford Site Integrated Stabilization Management Plan. Volume 1  

SciTech Connect (OSTI)

This document describes the plans of the Hanford Site for the safe interim storage of fissile materials. Currently, spent nuclear fuels reside in storage basins that have leaked in the past and are projected to leak in the future. Other problems in the basins include; sludge from decomposition, degraded cladding of fuel elements, and construction defects which make the basins seismically unsafe. This management plan describes the time and cost that it will take to implement a safe interim storage plan for the fissile materials.

McCormack, R.L.

1995-08-01T23:59:59.000Z

292

Experimental plan and construction guidance for Hanford Protective Barrier Test at Hill AFB, Utah  

SciTech Connect (OSTI)

Permanent isolation surface barriers are needed to fully isolate buried waste materials for long periods of time from the general environment. Multi-layer surface barriers that use natural earthen materials overlying bio-intrusion layers of rock and/or asphalt are expected to reduce infiltration or deep percolation to less than 0.5 mm (0.02 in.) of water. The layering also reduces root penetration, preventing uptake and translocation of hazardous materials to the surface vegetation. The opportunity exists to test the Hanford Barrier in a wetter, colder climate at an existing lysimeter facility located at Hill Air Force Base near Salt Lake, Utah. The use of an existing lysimeter facility simplifies the construction effort and allows comparison of the Hanford Protective Barrier with an existing US Environmental Protection Agency-Resource Conservation and Recovery Act clay cap already undergoing tests at the lysimeter site. This document presents the experimental plan for testing the Hanford Protective Barrier in a wetter, colder climate.

Kirkham, R.R.; Gee, G.W.

1994-04-01T23:59:59.000Z

293

Integrated method to create optimal dynamic strategic plans for corporate technology start-ups  

E-Print Network [OSTI]

This thesis presents an innovative method for evaluating and dynamically planning the development of uncertain technology investments. Its crux centers on a paradigm shift in the way managers assess investments, toward an ...

Mikati, Samir Omar

2009-01-01T23:59:59.000Z

294

Integrated Project Management Planning for the Deactivation of the Savannah River Site F-Canyon Complex  

SciTech Connect (OSTI)

This paper explains the planning process that is being utilized by the Westinghouse Savannah River Company to take the F-Canyon Complex facilities from operations to a deactivated condition awaiting final decommissioning.

Clark, T.G.

2000-12-01T23:59:59.000Z

295

Integrating regional strategic transportation planning and supply chain management : along the path to sustainability  

E-Print Network [OSTI]

A systems perspective for regional strategic transportation planning (RSTP) for freight movements involves an understanding of Supply Chain Management (SCM). This thesis argues that private sector freight shippers and ...

Sgouridis, Sgouris P

2005-01-01T23:59:59.000Z

296

Introducing the use of integrated Decision Support System in Natural Resources Planning  

E-Print Network [OSTI]

The target subject of Natural Resources Planning (NRP) includes various systems and their elements, all of which are centered around the natural resource system. Given this characteristic complexity and a high degree of ...

Park, Hye Yeon, S.M. Massachusetts Institute of Technology

2008-01-01T23:59:59.000Z

297

Implementation of the Integrated Planning Concept to Strengthen Indonesian Radiation Emergency Response Capabilities  

E-Print Network [OSTI]

Nuclear power has been included in Indonesian national plan as an alternative solution for electricity production. However, Indonesia lies within the Pacific Ring of Fire with around 129 active volcanoes along its region. In addition, the Indonesian...

Volia, Merinda Fitri

2014-07-30T23:59:59.000Z

298

Continuing the Validation of CCIM Processability for Glass Ceramic HLLW Forms: Plan for Test AFY14CCIM-GC1  

SciTech Connect (OSTI)

This test plan covers test AFY14CCIM-GC1which is the first of two scheduled FY-2014 test runs involving glass ceramic waste forms in the Idaho National Laboratory’s Cold Crucible Induction Melter Pilot Plant. The test plan is based on the successes and challenges of previous tests performed in FY-2012 and FY-2013. The purpose of this test is to continue to collect data for validating the glass ceramic High Level Liquid Waste form processability advantages using Cold Crucible Induction Melter technology. The major objective of AFYCCIM-GC1 is to complete additional proposed crucible pouring and post tapping controlled cooling experiments not completed during previous tests due to crucible drain failure. This is necessary to qualify that no heat treatments in standard waste disposal canisters are necessary for the operational scale production of glass ceramic waste forms. Other objectives include the production and post-test analysis of surrogate waste forms made from separate pours into the same graphite mold canister, testing the robustness of an upgraded crucible bottom drain and drain heater assembly, testing the effectiveness of inductive melt initiation using a resistive starter ring with a square wave configuration, and observing the tapped molten flow behavior in pans with areas identical to standard High Level Waste disposal canisters. Testing conditions, the surrogate waste composition, key testing steps, testing parameters, and sampling and analysis requirements are defined.

Vince Maio

2014-04-01T23:59:59.000Z

299

COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.1.3 Check Upload Integrity  

E-Print Network [OSTI]

COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.1.3 Check Upload Integrity Date. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Initial Release COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.1.3 Check Upload Integrity

Colorado at Boulder, University of

300

COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.1.3 Check Upload Integrity  

E-Print Network [OSTI]

COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.1.3 Check Upload Integrity Date. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Initial Release COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.1.3 Check Upload Integrity

Colorado at Boulder, University of

Note: This page contains sample records for the topic "integrated test plan" 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

IEEE TRANSACTIONS ON COMPUTER-AIDED DESIGN OF INTEGRATED CIRCUITS AND SYSTEMS, VOL. 25, NO. 7, JULY 2006 1289 Profile-Guided Microarchitectural Floor Planning  

E-Print Network [OSTI]

IEEE TRANSACTIONS ON COMPUTER-AIDED DESIGN OF INTEGRATED CIRCUITS AND SYSTEMS, VOL. 25, NO. 7, JULY 2006 1289 Profile-Guided Microarchitectural Floor Planning for Deep Submicron Processor Design Mongkol integration (VLSI) process tech- nology migrates to nanoscale with a feature size of less than 100 nm, global

Lim, Sung Kyu

302

Integral Benchmark Data for Nuclear Data Testing Through the ICSBEP & IRPhEP  

SciTech Connect (OSTI)

The status of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and International Reactor Physics Experiment Evaluation Project (IRPhEP) was last discussed directly with the nuclear data community at ND2007. Since ND2007, integral benchmark data that are available for nuclear data testing have increased significantly. The status of the ICSBEP and the IRPhEP is discussed and selected benchmark configurations that have been added to the ICSBEP and IRPhEP Handbooks since ND2007 are highlighted.

J. Blair Briggs; John D. Bess; Jim Gulliford; Ian Hill

2013-10-01T23:59:59.000Z

303

Simulation of a small break loss of coolant accident conducted at the BETHSY Integral Test Facility  

E-Print Network [OSTI]

. The computer code RELAP5/MOD3 was used to model the BETHSY Integral Test Facility for a. small break loss of coolant accident. This transient simulates a 2 inch cold leg break without high pressure safety injection, following the conditions of International..., and general input to my gra, duate education. TABLE OF CONTENTS CHAPTER Page I INTRODUCTION I. 1 Need for Investigation I. 2 Computational Modeling . I. 3 Experimental Modeling I, 4 International Cooperation . 1 3 RELAP5 CODE DESCRIPTION II. 1...

Bott, Charles Patrick

1992-01-01T23:59:59.000Z

304

Fabrication Control Plan for ORNL RH-LOCA ATF Test Specimens to be Irradiated in the ATR  

SciTech Connect (OSTI)

The purpose of this fabrication plan is (1) to summarize the design of a set of rodlets that will be fabricated and then irradiated in the Advanced Test Reactor (ATR) and (2) provide requirements for fabrication and acceptance criteria for inspections of the Light Water Reactor (LWR) – Accident Tolerant Fuels (ATF) rodlet components. The functional and operational (F&OR) requirements for the ATF program are identified in the ATF Test Plan. The scope of this document only covers fabrication and inspections of rodlet components detailed in drawings 604496 and 604497. It does not cover the assembly of these items to form a completed test irradiation assembly or the inspection of the final assembly, which will be included in a separate INL final test assembly specification/inspection document. The controls support the requirements that the test irradiations must be performed safely and that subsequent examinations must provide valid results.

Kevin G. Field; Richard Howard; Michael Teague

2014-06-01T23:59:59.000Z

305

Status of the RERTR program: overview, progress and plans. [Reduced Enrighment Research and Test Reactor  

SciTech Connect (OSTI)

The status of the US Reduced Enrichment Research and Test Reactor (RERTR) Program is reviewed. After a summary of the accomplishments which the RERTR Program had achieved by the end of 1984 with its many international partners, emphasis is placed on the progress achieved during 1985 and on current plans and schedules. A new miniplate series, concentrating on U/sub 3/Si/sub 2/-Al and U/sub 3/Si-Al fuels, was fabricated and is well into irradiation. The whole-core ORR demonstration is scheduled to begin in November 1985, with U/sub 3/Si/sub 2/-Al fuel at 4.8 g U/cm/sup 3/. Altogether, 921 full-size test and prototype elements have been ordered for fabrication with reduced enrichment and the new technologies. Qualification of U/sub 3/Si-Al fuel with approx.7 g U/cm/sup 3/ is still projected for 1989. This progress could not have been achieved without the close international cooperation which has existed since the beginning, and whose continuation and intensification will be essential to the achievement of the long-term RERTR goals.

Travelli, A.

1985-01-01T23:59:59.000Z

306

Test plan for evaluating the operational performance of the prototype nested, fixed-depth fluidic sampler  

SciTech Connect (OSTI)

The PHMC will provide Low Activity Wastes (LAW) tank wastes for final treatment by a privatization contractor from two double-shell feed tanks, 241-AP-102 and 241-AP-104. Concerns about the inability of the baseline ''grab'' sampling to provide large volume samples within time constraints has led to the development of a nested, fixed-depth sampling system. This sampling system will provide large volume, representative samples without the environmental, radiation exposure, and sample volume impacts of the current base-line ''grab'' sampling method. A plan has been developed for the cold testing of this nested, fixed-depth sampling system with simulant materials. The sampling system will fill the 500-ml bottles and provide inner packaging to interface with the Hanford Sites cask shipping systems (PAS-1 and/or ''safe-send''). The sampling system will provide a waste stream that will be used for on-line, real-time measurements with an at-tank analysis system. The cold tests evaluate the performance and ability to provide samples that are representative of the tanks' content within a 95 percent confidence interval, to sample while mixing pumps are operating, to provide large sample volumes (1-15 liters) within a short time interval, to sample supernatant wastes with over 25 wt% solids content, to recover from precipitation- and settling-based plugging, and the potential to operate over the 20-year expected time span of the privatization contract.

REICH, F.R.

1999-05-18T23:59:59.000Z

307

Integration of renewable energy sources: reliability-constrained power system planning and operations using computational intelligence  

E-Print Network [OSTI]

of cost, power dispatchability, and environmental impact. For instance, the intermittency of some renewable energy sources may compromise the system reliability when they are integrated into the traditional power grids. Thus, multiple issues should...

Wang, Lingfeng

2009-05-15T23:59:59.000Z

308

D-Site PRINCETON PLASMA TEST PLAN ISTP-NSTX-001  

E-Print Network [OSTI]

Planning Form #_______(ENG-032) Lockout/Tagout (ESH-016) Confined Space Permit (5008, Sec. 8, Chap 5) Lift

Princeton Plasma Physics Laboratory

309

Fuel and core testing plan for a target fueled isotope production reactor.  

SciTech Connect (OSTI)

In recent years there has been an unstable supply of the critical diagnostic medical isotope 99Tc. Several concepts and designs have been proposed to produce 99Mo the parent nuclide of 99Tc, at a commercial scale sufficient to stabilize the world supply. This work lays out a testing and experiment plan for a proposed 2 MW open pool reactor fueled by Low Enriched Uranium (LEU) 99Mo targets. The experiments and tests necessary to support licensing of the reactor design are described and how these experiments and tests will help establish the safe operating envelop for a medical isotope production reactor is discussed. The experiments and tests will facilitate a focused and efficient licensing process in order to bring on line a needed production reactor dedicated to supplying medical isotopes. The Target Fuel Isotope Reactor (TFIR) design calls for an active core region that is approximately 40 cm in diameter and 40 cm in fuel height. It contains up to 150 cylindrical, 1-cm diameter, LEU oxide fuel pins clad with Zircaloy (zirconium alloy), in an annular hexagonal array on a {approx}2.0 cm pitch surrounded, radially, by a graphite or a Be reflector. The reactor is similar to U.S. university reactors in power, hardware, and safety/control systems. Fuel/target pin fabrication is based on existing light water reactor fuel fabrication processes. However, as part of licensing process, experiments must be conducted to confirm analytical predictions of steady-state power and accident conditions. The experiment and test plan will be conducted in phases and will utilize existing facilities at the U.S. Department of Energy's Sandia National Laboratories. The first phase is to validate the predicted reactor core neutronics at delayed critical, zero power and very low power. This will be accomplished by using the Sandia Critical Experiment (CX) platform. A full scale TFIR core will be built in the CX and delayed critical measurements will be taken. For low power experiments, fuel pins can be removed after the experiment and using Sandia's metrology lab, relative power profiles (radially and axially) can be determined. In addition to validating neutronic analyses, confirming heat transfer properties of the target/fuel pins and core will be conducted. Fuel/target pin power limits can be verified with out-of-pile (electrical heating) thermal-hydraulic experiments. This will yield data on the heat flux across the Zircaloy clad and establish safety margin and operating limits. Using Sandia's Annular Core Research Reactor (ACRR) a 4 MW TRIGA type research reactor, target/fuel pins can be driven to desired fission power levels for long durations. Post experiment inspection of the pins can be conducted in the Auxiliary Hot Cell Facility to observe changes in the mechanical properties of the LEU matrix and burn-up effects. Transient tests can also be conducted at the ACRR to observe target/fuel pin performance during accident conditions. Target/fuel pins will be placed in double experiment containment and driven by pulsing the ACRR until target/fuel failure is observed. This will allow for extrapolation of analytical work to confirm safety margins.

Coats, Richard Lee; Dahl, James J.; Parma, Edward J., Jr.

2010-12-01T23:59:59.000Z

310

Modeling and Field Test Planning Activities in Support of Disposal of Heat-Generating Waste in Salt  

SciTech Connect (OSTI)

The modeling efforts in support of the field test planning conducted at LBNL leverage on recent developments of tools for modeling coupled thermal-hydrological-mechanical-chemical (THMC) processes in salt and their effect on brine migration at high temperatures. This work includes development related to, and implementation of, essential capabilities, as well as testing the model against relevant information and published experimental data related to the fate and transport of water. These are modeling capabilities that will be suitable for assisting in the design of field experiment, especially related to multiphase flow processes coupled with mechanical deformations, at high temperature. In this report, we first examine previous generic repository modeling results, focusing on the first 20 years to investigate the expected evolution of the different processes that could be monitored in a full-scale heater experiment, and then present new results from ongoing modeling of the Thermal Simulation for Drift Emplacement (TSDE) experiment, a heater experiment on the in-drift emplacement concept at the Asse Mine, Germany, and provide an update on the ongoing model developments for modeling brine migration. LBNL also supported field test planning activities via contributions to and technical review of framework documents and test plans, as well as participation in workshops associated with field test planning.

Rutqvist, Jonny; Blanco Martin, Laura; Mukhopadhyay, Sumit; Houseworth, Jim; Birkholzer, Jens

2014-09-26T23:59:59.000Z

311

Corrective Action Plan for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada  

SciTech Connect (OSTI)

Corrective Action Unit (CAU) 139, Waste Disposal Sites, is listed in the Federal Facility Agreement and Consent Order (FFACO) of 1996 (FFACO, 1996). CAU 139 consists of seven Corrective Action Sites (CASs) located in Areas 3, 4, 6, and 9 of the Nevada Test Site (NTS), which is located approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1). CAU 139 consists of the following CASs: CAS 03-35-01, Burn Pit; CAS 04-08-02, Waste Disposal Site; CAS 04-99-01, Contaminated Surface Debris; CAS 06-19-02, Waste Disposal Site/Burn Pit; CAS 06-19-03, Waste Disposal Trenches; CAS 09-23-01, Area 9 Gravel Gertie; and CAS 09-34-01, Underground Detection Station. Details of the site history and site characterization results for CAU 139 are provided in the approved Corrective Action Investigation Plan (CAIP) (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2006) and in the approved Corrective Action Decision Document (CADD) (NNSA/NSO, 2007). The purpose of this Corrective Action Plan (CAP) is to present the detailed scope of work required to implement the recommended corrective actions as specified in Section 4.0 of the approved CADD (NNSA/NSO, 2007). The approved closure activities for CAU 139 include removal of soil and debris contaminated with plutonium (Pu)-239, excavation of geophysical anomalies, removal of surface debris, construction of an engineered soil cover, and implementation of use restrictions (URs). Table 1 presents a summary of CAS-specific closure activities and contaminants of concern (COCs). Specific details of the corrective actions to be performed at each CAS are presented in Section 2.0 of this report.

NSTec Environmental Restoration

2007-07-01T23:59:59.000Z

312

Corrective Action Plan for Corrective Action Unit 417: Central Nevada Test Area Surface, Nevada  

SciTech Connect (OSTI)

This Corrective Action Plan provides methods for implementing the approved corrective action alternative as provided in the Corrective Action Decision Document for the Central Nevada Test Area (CNTA), Corrective Action Unit (CAU) 417 (DOE/NV, 1999). The CNTA is located in the Hot Creek Valley in Nye County, Nevada, approximately 137 kilometers (85 miles) northeast of Tonopah, Nevada. The CNTA consists of three separate land withdrawal areas commonly referred to as UC-1, UC-3, and UC-4, all of which are accessible to the public. CAU 417 consists of 34 Corrective Action Sites (CASs). Results of the investigation activities completed in 1998 are presented in Appendix D of the Corrective Action Decision Document (DOE/NV, 1999). According to the results, the only Constituent of Concern at the CNTA is total petroleum hydrocarbons (TPH). Of the 34 CASs, corrective action was proposed for 16 sites in 13 CASs. In fiscal year 1999, a Phase I Work Plan was prepared for the construction of a cover on the UC-4 Mud Pit C to gather information on cover constructibility and to perform site management activities. With Nevada Division of Environmental Protection concurrence, the Phase I field activities began in August 1999. A multi-layered cover using a Geosynthetic Clay Liner as an infiltration barrier was constructed over the UC-4 Mud Pit. Some TPH impacted material was relocated, concrete monuments were installed at nine sites, signs warning of site conditions were posted at seven sites, and subsidence markers were installed on the UC-4 Mud Pit C cover. Results from the field activities indicated that the UC-4 Mud Pit C cover design was constructable and could be used at the UC-1 Central Mud Pit (CMP). However, because of the size of the UC-1 CMP this design would be extremely costly. An alternative cover design, a vegetated cover, is proposed for the UC-1 CMP.

K. Campbell

2000-04-01T23:59:59.000Z

313

Project Management Plan for the Idaho National Engineering Laboratory Waste Isolation Pilot Plant Experimental Test Program  

SciTech Connect (OSTI)

EG&G Idaho, Inc. and Argonne National Laboratory-West (ANL-W) are participating in the Idaho National Engineering Laboratory`s (INEL`s) Waste Isolation Pilot Plant (WIPP) Experimental Test Program (WETP). The purpose of the INEL WET is to provide chemical, physical, and radiochemical data on transuranic (TRU) waste to be stored at WIPP. The waste characterization data collected will be used to support the WIPP Performance Assessment (PA), development of the disposal No-Migration Variance Petition (NMVP), and to support the WIPP disposal decision. The PA is an analysis required by the Code of Federal Regulations (CFR), Title 40, Part 191 (40 CFR 191), which identifies the processes and events that may affect the disposal system (WIPP) and examines the effects of those processes and events on the performance of WIPP. A NMVP is required for the WIPP by 40 CFR 268 in order to dispose of land disposal restriction (LDR) mixed TRU waste in WIPP. It is anticipated that the detailed Resource Conservation and Recovery Act (RCRA) waste characterization data of all INEL retrievably-stored TRU waste to be stored in WIPP will be required for the NMVP. Waste characterization requirements for PA and RCRA may not necessarily be identical. Waste characterization requirements for the PA will be defined by Sandia National Laboratories. The requirements for RCRA are defined in 40 CFR 268, WIPP RCRA Part B Application Waste Analysis Plan (WAP), and WIPP Waste Characterization Program Plan (WWCP). This Project Management Plan (PMP) addresses only the characterization of the contact handled (CH) TRU waste at the INEL. This document will address all work in which EG&G Idaho is responsible concerning the INEL WETP. Even though EG&G Idaho has no responsibility for the work that ANL-W is performing, EG&G Idaho will keep a current status and provide a project coordination effort with ANL-W to ensure that the INEL, as a whole, is effectively and efficiently completing the requirements for WETP.

Connolly, M.J.; Sayer, D.L.

1993-11-01T23:59:59.000Z

314

Towards an Integrated Planning and Adaptive Resource Management Architecture for Distributed Real-time Embedded Systems  

E-Print Network [OSTI]

conditions change. Key challenges in managing open DRE systems in- clude effective planning and online management of system resources to accommodate for changing mission goals, en- vironmental conditions- source management to control and ensure efficient function- ing of open DRE systems. 1 Introduction

Koutsoukos, Xenofon D.

315

Integral and Separate Effects Tests for Thermal Hydraulics Code Validation for Liquid-Salt Cooled Nuclear Reactors  

SciTech Connect (OSTI)

The objective of the 3-year project was to collect integral effects test (IET) data to validate the RELAP5-3D code and other thermal hydraulics codes for use in predicting the transient thermal hydraulics response of liquid salt cooled reactor systems, including integral transient response for forced and natural circulation operation. The reference system for the project is a modular, 900-MWth Pebble Bed Advanced High Temperature Reactor (PB-AHTR), a specific type of Fluoride salt-cooled High temperature Reactor (FHR). Two experimental facilities were developed for thermal-hydraulic integral effects tests (IETs) and separate effects tests (SETs). The facilities use simulant fluids for the liquid fluoride salts, with very little distortion to the heat transfer and fluid dynamics behavior. The CIET Test Bay facility was designed, built, and operated. IET data for steady state and transient natural circulation was collected. SET data for convective heat transfer in pebble beds and straight channel geometries was collected. The facility continues to be operational and will be used for future experiments, and for component development. The CIET 2 facility is larger in scope, and its construction and operation has a longer timeline than the duration of this grant. The design for the CIET 2 facility has drawn heavily on the experience and data collected on the CIET Test Bay, and it was completed in parallel with operation of the CIET Test Bay. CIET 2 will demonstrate start-up and shut-down transients and control logic, in addition to LOFC and LOHS transients, and buoyant shut down rod operation during transients. Design of the CIET 2 Facility is complete, and engineering drawings have been submitted to an external vendor for outsourced quality controlled construction. CIET 2 construction and operation continue under another NEUP grant. IET data from both CIET facilities is to be used for validation of system codes used for FHR modeling, such as RELAP5-3D. A set of numerical models were developed in parallel to the experimental work. RELAP5-3D models were developed for the salt-cooled PB-AHTR, and for the simulat fluid CIET natural circulation experimental loop. These models are to be validated by the data collected from CIET. COMSOL finite element models were used to predict the temperature and fluid flow distribution in the annular pebble bed core; they were instrumental for design of SETs, and they can be used for code-to-code comparisons with RELAP5-3D. A number of other small SETs, and numerical models were constructed, as needed, in support of this work. The experiments were designed, constructed and performed to meet CAES quality assurance requirements for test planning, implementation, and documentation; equipment calibration and documentation, procurement document control; training and personnel qualification; analysis/modeling software verification and validation; data acquisition/collection and analysis; and peer review.

Peterson, Per

2012-10-30T23:59:59.000Z

316

Integrated project management plan for the Plutonium Finishing Plant stabilization and deactivation project  

SciTech Connect (OSTI)

This document sets forth the plans, organization, and control systems for managing the PFP Stabilization and Deactivation Project, and includes the top level cost and schedule baselines. The project includes the stabilization of Pu-bearing materials, storage, packaging, and transport of these and other nuclear materials, surveillance and maintenance of facilities and systems relied upon for storage of the materials, and transition of the facilities in the PFP Complex.

SINCLAIR, J.C.

1999-05-03T23:59:59.000Z

317

The RERTR (Reduced Enrichment Research and Test Reactor) Program: Progress and plans  

SciTech Connect (OSTI)

The progress of the Reduced Enrichment Research and Test Reactor (RERTR) Program is described. After a brief summary of the results which the RERTR Program, in collaboration with its many international partners, had achieved by the end of 1986, the activities, results, and new developments which occurred in 1987 are reviewed. Irradiation of the second miniplate series, concentrating on U/sub 3/Si/sub 2/-Al and U/sub 3/Si-Al fuels, was completed and postirradiation examinations were performed on many of its miniplates. The whole-core ORR demonstration with U/sub 3/Si/sub 2/-Al fuel at 4.8 g U/cm/sup 3/ was completed at the end of March with excellent results and with 29 elements estimated to have reached at least 40% average burnup. Good progress was made in the area of LEU usage for the production of fission /sup 99/Mo, and in the coordination of safety evaluations related to LEU conversions of US university reactors. Planned activities include testing and demonstrating advanced fuels intended to allow use of reduced enrichment uranium in very-high-performance reactors. Two candidate fuels are U/sub 3/Si-Al with 19.75% enrichment and U/sub 3/Si/sub 2/-Al with 45% enrichment. Demonstration of these fuels will include irradiation of full-size elements and, possibly, a full-core demonstration. Achievement of the final program goals is still projected for 1990. This progress could not have been possible without the close international cooperation which has existed from the beginning, and which is essential to the ultimate success of the RERTR Program.

Travelli, A.

1987-01-01T23:59:59.000Z

318

An Agent-Based Test Bed for the Integrated Study of Retail and Wholesale Power System Operations  

E-Print Network [OSTI]

An Agent-Based Test Bed for the Integrated Study of Retail and Wholesale Power System Operations D study of retail and wholesale power markets operating over transmission and distribution networks with smart-grid functionality. The test bed will seam together two existing test beds, the AMES Wholesale

Tesfatsion, Leigh

319

Landscape and Urban Planning 78 (2006) 5070 Room for rivers: An integrative search  

E-Print Network [OSTI]

for floodplain restoration S. Rohdea,, M. Hostmannb, A. Peterc, K.C. Ewaldd a Swiss Federal Institute for Forest restoration aims to re-establish the ecological integrity of a river ecosystem. However, restoration measures to identify stream systems where present environmental (e.g. natural flow, sufficient bed load material

320

Spent nuclear fuel integrity during dry storage - performance tests and demonstrations  

SciTech Connect (OSTI)

This report summarizes the results of fuel integrity surveillance determined from gas sampling during and after performance tests and demonstrations conducted from 1983 through 1996 by or in cooperation with the US DOE Office of Commercial Radioactive Waste Management (OCRWM). The cask performance tests were conducted at Idaho National Engineering Laboratory (INEL) between 1984 and 1991 and included visual observation and ultrasonic examination of the condition of the cladding, fuel rods, and fuel assembly hardware before dry storage and consolidation of fuel, and a qualitative determination of the effects of dry storage and fuel consolidation on fission gas release from the spent fuel rods. The performance tests consisted of 6 to 14 runs involving one or two loading, usually three backfill environments (helium, nitrogen, and vacuum backfills), and one or two storage system orientations. The nitrogen and helium backfills were sampled and analyzed to detect leaking spent fuel rods. At the end of each performance test, periodic gas sampling was conducted on each cask. A spent fuel behavior project (i.e., enhanced surveillance, monitoring, and gas sampling activities) was initiated by DOE in 1994 for intact fuel in a CASTOR V/21 cask and for consolidated fuel in a VSC-17 cask. The results of the gas sampling activities are included in this report. Information on spent fuel integrity is of interest in evaluating the impact of long-term dry storage on the behavior of spent fuel rods. Spent fuel used during cask performance tests at INEL offers significant opportunities for confirmation of the benign nature of long-term dry storage. Supporting cask demonstration included licensing and operation of an independent spent fuel storage installation (ISFSI) at the Virginia Power (VP) Surry reactor site. A CASTOR V/21, an MC-10, and a Nuclear Assurance NAC-I28 have been loaded and placed at the VP ISFSI as part of the demonstration program. 13 refs., 14 figs., 9 tabs.

McKinnon, M.A.; Doherty, A.L.

1997-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "integrated test plan" from the National Library of EnergyBeta (NLEBeta).
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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

Corrective Action Plan for Corrective Action Unit 543: Liquid Disposal Units, Nevada Test Site, Nevada  

SciTech Connect (OSTI)

Corrective Action Unit (CAU) 543: Liquid Disposal Units is listed in Appendix III of the ''Federal Facility Agreement and Consent Order'' (FFACO) which was agreed to by the state of Nevada, the U.S. Department of Energy (DOE), and the U.S. Department of Defense (FFACO, 1996). CAU 543 sites are located in Areas 6 and 15 of the Nevada Test Site (NTS), which is approximately 65 miles northwest of Las Vegas, Nevada. CAU 543 consists of the following seven Corrective Action Sites (CASs) (Figure 1): CAS 06-07-01, Decon Pad; CAS 15-01-03, Aboveground Storage Tank; CAS 15-04-01, Septic Tank; CAS 15-05-01, Leachfield; CAS 15-08-01, Liquid Manure Tank; CAS 15-23-01, Underground Radioactive Material Area; and CAS 15-23-03, Contaminated Sump, Piping. All Area 15 CASs are located at the former U.S. Environmental Protection Agency (EPA) Farm, which operated from 1963 to 1981 and was used to support animal experiments involving the uptake of radionuclides. Each of the Area 15 CASs, except CAS 15-23-01, is associated with the disposal of waste effluent from Building 15-06, which was the primary location of the various tests and experiments conducted onsite. Waste effluent disposal from Building 15-06 involved piping, sumps, outfalls, a septic tank with leachfield, underground storage tanks, and an aboveground storage tank (AST). CAS 15-23-01 was associated with decontamination activities of farm equipment potentially contaminated with radiological constituents, pesticides, and herbicides. While the building structures were removed before the investigation took place, all the original tanks, sumps, piping, and concrete building pads remain in place. The Area 6 CAS is located at the Decontamination Facility in Area 6, a facility which operated from 1971 to 2001 and was used to decontaminate vehicles, equipment, clothing, and other materials that had become contaminated during nuclear testing activities. The CAS includes the effluent collection and distribution systems for Buildings 6-605, 6-606, and 6-607, which consists of septic tanks, sumps, piping, floor drains, drain trenches, cleanouts, and a concrete foundation. Additional details of the site history are provided in the CAU 543 Corrective Action Investigation Plan (CAIP) (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2004a), and the CAU 543 Corrective Action Decision Document (CADD) (NNSA/NSO, 2005).

NSTec Environmental Restoration

2007-04-01T23:59:59.000Z

322

Engineering Work Plan for the Development of Phased Startup Initiative (PSI) Phases 3 and 4 Test Equipment  

SciTech Connect (OSTI)

A number of tools and equipment pieces are required to facilitate planned test operations during Phases 3 and 4 of the Phased Startup Initiative (PSI). These items will be used in assessing residual canister sludge quantities on cleaned fuel assemblies, sorting coarse and fine scrap fuel pieces, assessing the size distribution of scrap pieces, loading scrap into a canister, and measuring the depth of the accumulated scrap in a canister. This work plan supercedes those previously issued for development of several of these test items. These items will be considered prototype equipment until testing has confirmed their suitability for use in K West Basin. The process described in AP-EN-6-032 will be used to qualify the equipment for facility use. These items are considered non-OCRWM for PSI Phase 3 applications. The safety classification of this equipment is General Service, with Quality Level 0 (for PSI Phase 3). Quality Control inspections shall be performed to verify basic dimensions and overall configurations of fabricated components, and any special quality control verifications specified in this work plan (Section 3.1.5). These inspections shall serve to approve the test equipment for use in K West Basin (Acceptance Tag). This equipment is for information gathering only during PSI Phases 3 and 4 activities, and will be discarded at the completion of PSI. For equipment needed to support actual production throughput, development/fabrication/testing activities would be more rigorously controlled.

PITNER, A.L.

2000-04-11T23:59:59.000Z

323

Test plan for evaluation of plasma melter technology for vitrification of high-sodium content low-level radioactive liquid wastes  

SciTech Connect (OSTI)

This document provides a test plan for the conduct of plasma arc vitrification testing by a vendor in support of the Hanford Tank Waste Remediation System (TWRS) Low-Level Waste (LLW) Vitrification Program. The vendor providing this test plan and conducting the work detailed within it [one of seven selected for glass melter testing under Purchase Order MMI-SVV-384212] is the Westinghouse Science and Technology Center (WSTC) in Pittsburgh, PA. WSTC authors of the test plan are D. F. McLaughlin, E. J. Lahoda, W. R. Gass, and N. D`Amico. The WSTC Program Manager for this test is D. F. McLaughlin. This test plan is for Phase I activities described in the above Purchase Order. Test conduct includes melting of glass frit with Hanford LLW Double-Shell Slurry Feed waste simulant in a plasma arc fired furnace.

McLaughlin, D.F.; Lahoda, E.J.; Gass, W.R.; D`Amico, N. [ed.

1994-10-20T23:59:59.000Z

324

Test plan for glass melter system technologies for vitrification of high-sodium content low-level radioactive liquid waste, Project No. RDD-43288  

SciTech Connect (OSTI)

This document provides a test plan for the conduct of combustion fired cyclone vitrification testing by a vendor in support of the Hanford Tank Waste Remediation System, Low-Level Waste Vitrification Program. The vendor providing this test plan and conducting the work detailed within it is the Babcock & Wilcox Company Alliance Research Center in Alliance, Ohio. This vendor is one of seven selected for glass melter testing.

Higley, B.A.

1995-03-15T23:59:59.000Z

325

Barrier erosion control test plan: Gravel mulch, vegetation, and soil water interactions  

SciTech Connect (OSTI)

Soil erosion could reduce the water storage capacity of barriers that have been proposed for the disposal of near-surface waste at the US Department of Energy's Hanford Site. Gravel mixed into the top soil surface may create a self-healing veneer that greatly retards soil loss. However, gravel admixtures may also enhance infiltration of rainwater, suppress plant growth and water extraction, and lead to the leaching of underlying waste. This report describes plans for two experiments that were designed to test hypotheses concerning the interactive effects of surface gravel admixtures, revegetation, and enhanced precipitation on soil water balance and plant abundance. The first experiment is a factorial field plot set up on the site selected as a soil borrow area for the eventual construction of barriers. The treatments, arranged in a a split-split-plot design structure, include two densities of gravel admix, a mixture of native and introduced grasses, and irrigation to simulate a wetter climate. Changes in soil water storage and plant cover are monitored with neutron moisture probes and point intercept sampling, respectively. The second experiment consists of an array of 80 lysimeters containing several different barrier prototypes. Surface treatments are similar to the field-plot experiment. Drainage is collected from a valve at the base of each lysimeter tube, and evapotranspiration is estimated by subtraction. The lysimeters are also designed to be coupled to a whole-plant gas exchange system that will be used to conduct controlled experiments on evapotranspiration for modeling purposes. 56 refs., 6 figs., 8 tabs.

Waugh, W.J.; Link, S.O. (Pacific Northwest Lab., Richland, WA (USA))

1988-07-01T23:59:59.000Z

326

Integration of Rooftop Photovoltaic Systems in St. Paul Ford Sites Redevelopment Plans  

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

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

327

Streamlined Approach for Environmental Restoration Work Plan for Corrective Action Unit 461: Joint Test Assembly Sites and Corrective Action Unit 495: Unconfirmed Joint Test Assembly Sites Tonopah Test Range, Nevada  

SciTech Connect (OSTI)

This Streamlined Approach for Environmental Restoration plan addresses the action necessary for the clean closure of Corrective Action Unit 461 (Test Area Joint Test Assembly Sites) and Corrective Action Unit 495 (Unconfirmed Joint Test Assembly Sites). The Corrective Action Units are located at the Tonopah Test Range in south central Nevada. Closure for these sites will be completed by excavating and evaluating the condition of each artillery round (if found); detonating the rounds (if necessary); excavating the impacted soil and debris; collecting verification samples; backfilling the excavations; disposing of the impacted soil and debris at an approved low-level waste repository at the Nevada Test Site

Jeff Smith

1998-08-01T23:59:59.000Z

328

Use of Frequency Response Metrics to Assess the Planning and Operating Requirements for Reliable Integration of Variable Renewable Generation  

E-Print Network [OSTI]

Report - 2006 Minnesota Wind Integration Study Volume I.NREL). 2010. Eastern Wind Integration and TransmissionAvista Corporation Wind Integration Study. March. http://

Eto, Joseph H.

2011-01-01T23:59:59.000Z

329

CORRECTIVE ACTION PLAN FOR CORRECTIVE ACTION UNIT 543: LIQUID DISPOSAL UNITS, NEVADA TEST SITE, NEVADA  

SciTech Connect (OSTI)

The purpose of this Corrective Action Plan is to provide the detailed scope of work required to implement the recommended corrective actions as specified in the approved Corrective Action Decision Document.

NONE

2006-09-01T23:59:59.000Z

330

CORRECTIVE ACTION PLAN FOR CORRECTIVE ACTION UNIT 300: SURFACE RELEASE AREAS NEVADA TEST SITE, NEVADA  

SciTech Connect (OSTI)

The purpose of this Corrective Action Plan (CAP) is to provide the detailed scope of work required to implement the recommended corrective actions as specified in the approved CAU 300 CADD.

NONE

2006-07-01T23:59:59.000Z

331

Integrated testing of the Thales LPT9510 pulse tube cooler and the iris LCCE electronics  

SciTech Connect (OSTI)

The Jet Propulsion Laboratory (JPL) has identified the Thales LPT9510 pulse tube cryocooler as a candidate low cost cryocooler to provide active cooling on future cost-capped scientific missions. The commercially available cooler can provide refrigeration in excess of 2 W at 100K for 60W of power. JPL purchased the LPT9510 cooler for thermal and dynamic performance characterization, and has initiated the flight qualification of the existing cooler design to satisfy near-term JPL needs for this cooler. The LPT9510 has been thermally tested over the heat reject temperature range of 0C to +40C during characterization testing. The cooler was placed on a force dynamometer to measure the selfgenerated vibration of the cooler. Iris Technology has provided JPL with a brass board version of the Low Cost Cryocooler Electronics (LCCE) to drive the Thales cooler during characterization testing. The LCCE provides precision closed-loop temperature control and embodies extensive protection circuitry for handling and operational robustness; other features such as exported vibration mitigation and low frequency input current filtering are envisioned as options that future flight versions may or may not include based upon the mission requirements. JPL has also chosen to partner with Iris Technology for the development of electronics suitable for future flight applications. Iris Technology is building a set of radiation-hard, flight-design electronics to deliver to the Air Force Research Laboratory (AFRL). Test results of the thermal, dynamic and EMC testing of the integrated Thales LPT9510 cooler and Iris LCCE electronics is presented here.

Johnson, Dean L.; Rodriguez, Jose I.; Carroll, Brian A. [The Jet Propulsion Laboratory, California Institute of Technology, Pasadena, CA 91109 (United States); Bustamante, John G. [Georgia Institute of Technology, Atlanta, GA 30332 (United States); Kirkconnell, Carl S.; Luong, Thomas T.; Murphy, J. B.; Haley, Michael F. [Iris Technology, Irvine, CA 92616 (United States)

2014-01-29T23:59:59.000Z

332

Integrated Task Plans for the Hanford Environmental Dose Reconstruction Project, FY 1992 through May 1994  

SciTech Connect (OSTI)

The purpose of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate radiation doses from Hanford Site operations since 1944 to populations and individuals. The primary objective of work to be performed through May 1994 is to (1) determine the project's appropriate scope (space, time, radionuclides, pathways and individuals/population groups), (2) determine the project's appropriate level of accuracy (level of uncertainty in dose estimates) for the project, (3) complete model and data development, and (4) estimate doses for the Hanford Thyroid Disease Study (HTDS), representative individuals, and special populations as described herein. The plan for FY 1992 through May 1994 has been prepared based on activities and budgets approved by the Technical Steering Panel (TSP) at its meetings on August 19--20, 1991, and April 23--25, 1992. The activities can be divided into four broad categories: (1) model and data evaluation activities, (2)additional dose estimates, (3) model and data development activities, and (4)technical and communication support.

Shipler, D.B.

1992-09-01T23:59:59.000Z

333

A Comparison of 2pi and 4pi Photometric Testing of Directional and Omnidirectional Sources in an Integrating Sphere  

SciTech Connect (OSTI)

A Comparison of 2pi and 4pi Photometric Testing of Directional and Omnidirectional Sources in an Integrating Sphere. These data will help determine if differences in methods should be addresed in test methods specifically for LED products but applicable to other technologies as well

Richman, Eric E.; Merzouk, Massine B.

2014-06-12T23:59:59.000Z

334

Oxy-Combustion Burner and Integrated Pollutant Removal Research and Development Test Facility  

SciTech Connect (OSTI)

A high flame temperature oxy-combustion test facility consisting of a 5 MWe equivalent test boiler facility and 20 KWe equivalent IPR® was constructed at the Hammond, Indiana manufacturing site. The test facility was operated natural gas and coal fuels and parametric studies were performed to determine the optimal performance conditions and generated the necessary technical data required to demonstrate the technologies are viable for technical and economic scale-up. Flame temperatures between 4930-6120F were achieved with high flame temperature oxy-natural gas combustion depending on whether additional recirculated flue gases are added to balance the heat transfer. For high flame temperature oxy-coal combustion, flame temperatures in excess of 4500F were achieved and demonstrated to be consistent with computational fluid dynamic modeling of the burner system. The project demonstrated feasibility and effectiveness of the Jupiter Oxygen high flame temperature oxy-combustion process with Integrated Pollutant Removal process for CCS and CCUS. With these technologies total parasitic power requirements for both oxygen production and carbon capture currently are in the range of 20% of the gross power output. The Jupiter Oxygen high flame temperature oxy-combustion process has been demonstrated at a Technology Readiness Level of 6 and is ready for commencement of a demonstration project.

Mark Schoenfield; Manny Menendez; Thomas Ochs; Rigel Woodside; Danylo Oryshchyn

2012-09-30T23:59:59.000Z

335

Test plan for N2 HEPA filters assembly shop stock used on PFP E4 exhaust system  

SciTech Connect (OSTI)

At Plutonium Finishing Plant (PFP) and Plutonium Reclamation Facility (PRF) Self-contained HEPA filters, encased in wooden frames and boxes, are installed in the E4 Exhaust Ventilation System to provide confinement of radioactive releases to the environment and confinement of radioactive contamination within designated zones inside the facility. Recently during the routine testing in-leakage was discovered downstream of the Self-contained HEPA filters boxes. This Test Plan describes the approach to conduct investigation of the root causes for the in-leakage of HEPA filters.

DICK, J.D.

1999-09-01T23:59:59.000Z

336

An experimental test plan for the characterization of molten salt thermochemical properties in heat transport systems  

SciTech Connect (OSTI)

Molten salts are considered within the Very High Temperature Reactor program as heat transfer media because of their intrinsically favorable thermo-physical properties at temperatures starting from 300 C and extending up to 1200 C. In this context two main applications of molten salt are considered, both involving fluoride-based materials: as primary coolants for a heterogeneous fuel reactor core and as secondary heat transport medium to a helium power cycle for electricity generation or other processing plants, such as hydrogen production. The reference design concept here considered is the Advanced High Temperature Reactor (AHTR), which is a large passively safe reactor that uses solid graphite-matrix coated-particle fuel (similar to that used in gas-cooled reactors) and a molten salt primary and secondary coolant with peak temperatures between 700 and 1000 C, depending upon the application. However, the considerations included in this report apply to any high temperature system employing fluoride salts as heat transfer fluid, including intermediate heat exchangers for gas-cooled reactor concepts and homogenous molten salt concepts, and extending also to fast reactors, accelerator-driven systems and fusion energy systems. The purpose of this report is to identify the technical issues related to the thermo-physical and thermo-chemical properties of the molten salts that would require experimental characterization in order to proceed with a credible design of heat transfer systems and their subsequent safety evaluation and licensing. In particular, the report outlines an experimental R&D test plan that would have to be incorporated as part of the design and operation of an engineering scaled facility aimed at validating molten salt heat transfer components, such as Intermediate Heat Exchangers. This report builds on a previous review of thermo-physical properties and thermo-chemical characteristics of candidate molten salt coolants that was generated as part of the same project [1]. However, this work focuses on two materials: the LiF-BeF2 eutectic (67 and 33 mol%, respectively, also known as flibe) as primary coolant and the LiF-NaF-KF eutectic (46.5, 11.5, and 52 mol%, respectively, also known as flinak) as secondary heat transport fluid. At first common issues are identified, involving the preparation and purification of the materials as well as the development of suitable diagnostics. Than issues specific to each material and its application are considered, with focus on the compatibility with structural materials and the extension of the existing properties database.

Pattrick Calderoni

2010-09-01T23:59:59.000Z

337

Corrective Action Plan for Corrective Action Unit 563: Septic Systems, Nevada Test Site, Nevada  

SciTech Connect (OSTI)

This Corrective Action Plan (CAP) has been prepared for Corrective Action Unit (CAU) 563, Septic Systems, in accordance with the Federal Facility Agreement and Consent Order. CAU 563 consists of four Corrective Action Sites (CASs) located in Areas 3 and 12 of the Nevada Test Site. CAU 563 consists of the following CASs: #2; CAS 03-04-02, Area 3 Subdock Septic Tank #2; CAS 03-59-05, Area 3 Subdock Cesspool #2; CAS 12-59-01, Drilling/Welding Shop Septic Tanks #2; CAS 12-60-01, Drilling/Welding Shop Outfalls Site characterization activities were performed in 2007, and the results are presented in Appendix A of the CAU 563 Corrective Action Decision Document. The scope of work required to implement the recommended closure alternatives is summarized below. #2; CAS 03-04-02, Area 3 Subdock Septic Tank, contains no contaminants of concern (COCs) above action levels. No further action is required for this site; however, as a best management practice (BMP), all aboveground features (e.g., riser pipes and bumper posts) will be removed, the septic tank will be removed, and all open pipe ends will be sealed with grout. #2; CAS 03-59-05, Area 3 Subdock Cesspool, contains no COCs above action levels. No further action is required for this site; however, as a BMP, all aboveground features (e.g., riser pipes and bumper posts) will be removed, the cesspool will be abandoned by filling it with sand or native soil, and all open pipe ends will be sealed with grout. #2; CAS 12-59-01, Drilling/Welding Shop Septic Tanks, will be clean closed by excavating approximately 4 cubic yards (yd3) of arsenic- and chromium-impacted soil. In addition, as a BMP, the liquid in the South Tank will be removed, the North Tank will be removed or filled with grout and left in place, the South Tank will be filled with grout and left in place, all open pipe ends will be sealed with grout or similar material, approximately 10 yd3 of chlordane-impacted soil will be excavated, and debris within the CAS boundary will be removed. #2; CAS 12-60-01, Drilling/Welding Shop Outfalls, contains no COCs above action levels. No further action is required for this site; however, as a BMP, three drain pipe openings will be sealed with grout.

NSTec Environmental Restoration

2009-03-31T23:59:59.000Z

338

Development, tests, and data acquisition of the integrated system of internal sensors for RFX  

SciTech Connect (OSTI)

The RFX reversed field pinch (RFP) has undergone major modifications of the load assembly and is now equipped with a large number of active external coils for magnetohydrodynamics mode control. The study of the effects on the plasma of both the new passive structure and the active coils is then of great importance, as well as the investigation of turbulence due to its influence on plasma transport. An integrated system of magnetic, electrostatic and calorimetric sensors has been realized, fulfilling very challenging requirements in terms of spatial and temporal resolution, which are characteristic features of RFP plasmas. A description of the whole diagnostic system is given, including the original solutions adopted to cope with the limited space available and the thermal and electrical requirements, particularly for the calorimetrical probes. The tests performed on the whole system during the installation are presented. Signal conditioning and data acquisition are described.

Serianni, G.; Bolzonella, T.; Cavazzana, R.; Marchiori, G.; Pomaro, N.; Lotto, L.; Monari, M.; Taliercio, C. [Consorzio RFX, Associazione Euratom-ENEA sulla Fusione, Corso Stati Uniti 4, I-35127 Padova (Italy)

2004-10-01T23:59:59.000Z

339

Evaluation of Maxim Module-Integrated Electronics at the DOE Regional Test Centers (Presentation)  

SciTech Connect (OSTI)

Module-embedded power electronics developed by Maxim Integrated are under evaluation through a partnership with the Department of Energy's Regional Test Center (RTC) program. Field deployments of both conventional modules and electronics-enhanced modules are designed to quantify the performance advantage of Maxim's products under different amounts of interrow shading, and their ability to be deployed at a greater ground-coverage ratio than conventional modules. Simulations in PVSYST have quantified the predicted performance difference between conventional modules and Maxim's modules from interrow shading. Initial performance results have identified diffuse irradiance losses at tighter row spacing for both the Maxim and conventional modules. Comparisons with published models show good agreement with models predicting the greatest diffuse irradiance losses. At tighter row spacing, all of the strings equipped with embedded power electronics outperformed their conventional peers. An even greater performance advantage is predicted to occur in the winter months when the amount of interrow shading mismatch is at a maximum.

Deline, C.; Sekulic, B.; Barkaszi, S.; Yang, J.; Kahn, S.

2014-06-01T23:59:59.000Z

340

Effective early planning and integration of NEPA into the decision-making process  

SciTech Connect (OSTI)

This paper covers several key challenges and lessons learned in a federal agency assignment to educate the decision makers in NEPA and then to effectuate decisions early in the decision-making process based on the information derived from the NEPA process participants and documentation. Many of the key challenges faced by these federal decision makers stem, in part, from unfamiliarity with NEPA requirements and the benefits that can be derived by utilizing the process to support making an informed decision. Secondly, federal managers, at times believe that the process is a hindrance to accomplishing their mission. Lastly, there was a genuine belief that the public and other organizations within the agency should have no part in evaluating or commenting on the proposed action. Using the knowledge gained from drafting and reviewing EISs and EAs, Booz, Allen devised a systematic process that effectively: educated management on NEPA requirements; developed a management tool to guide and integrate the process; and encouraged the early and effective use of environmental and social information into all decision-making processes.

Hannon, W.C.; Gensler, J.D. (Allen and Hamilton, Inc., Bethesda, MD (United States))

1993-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "integrated test plan" 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

Design and Application of an Electronic Logbook for Space System Integration and Test Operations  

SciTech Connect (OSTI)

In the highly technological aerospace world paper is still widely used to document space system integration and test (I&T) operations. E-Logbook is a new technology designed to substitute the most commonly used paper logbooks in space system I&T, such as the connector mate/demate logbook, the flight hardware and flight software component installation logbook, the material mix record logbook and the electronic ground support equipment validation logbook. It also includes new logbook concepts, such as the shift logbook, which optimizes management oversight and the shift hand-over process, and the configuration logbook, which instantly reports on the global I&T state of the space system before major test events or project reviews. The design of E-Logbook focuses not only on a reliable and efficient relational database, but also on an ergonomic human-computer interactive (HCI) system that can help reduce human error and improve I&T management and oversight overall. E-Logbook has been used for the I&T operation of the Gamma-ray Large Area Space Telescope (GLAST) Large Area Telescope (LAT) at the Stanford Linear Accelerator Center (SLAC). More than 41,000 records have been created for the different I&T logbooks, with no data having been corrupted or critically lost. 94% of the operators and 100% of the management exposed to E-Logbook prefer it to paper logbooks and recommend its use in the aerospace industry.

Kavelaars, Alicia T.; /SLAC /Stanford U., Dept. Aeronaut. Astronaut.; ,

2006-10-10T23:59:59.000Z

342

Design of an Integrated Laboratory Scale Test for Hydrogen Production via High Temperature Electrolysis  

SciTech Connect (OSTI)

The Idaho National Laboratory (INL) is researching the feasibility of high-temperature steam electrolysis for high-efficiency carbon-free hydrogen production using nuclear energy. Typical temperatures for high-temperature electrolysis (HTE) are between 800º-900ºC, consistent with anticipated coolant outlet temperatures of advanced high-temperature nuclear reactors. An Integrated Laboratory Scale (ILS) test is underway to study issues such as thermal management, multiple-stack electrical configuration, pre-heating of process gases, and heat recuperation that will be crucial in any large-scale implementation of HTE. The current ILS design includes three electrolysis modules in a single hot zone. Of special design significance is preheating of the inlet streams by superheaters to 830°C before entering the hot zone. The ILS system is assembled on a 10’ x 16’ skid that includes electronics, power supplies, air compressor, pumps, superheaters, , hot zone, condensers, and dew-point sensor vessels. The ILS support system consists of three independent, parallel supplies of electrical power, sweep gas streams, and feedstock gas mixtures of hydrogen and steam to the electrolysis modules. Each electrolysis module has its own support and instrumentation system, allowing for independent testing under different operating conditions. The hot zone is an insulated enclosure utilizing electrical heating panels to maintain operating conditions. The target hydrogen production rate for the ILS is 5000 Nl/hr.

G.K. Housley; K.G. Condie; J.E. O'Brien; C. M. Stoots

2007-06-01T23:59:59.000Z

343

Corrective Action Investigation Plan for Corrective Action Unit 528: Polychlorinated Biphenyls Contamination, Nevada Test Site, Nevada, Rev. 0  

SciTech Connect (OSTI)

This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 528, Polychlorinated Biphenyls Contamination (PCBs), Nevada Test Site (NTS), Nevada, under the Federal Facility Agreement and Consent Order. Located in the southwestern portion of Area 25 on the NTS in Jackass Flats (adjacent to Test Cell C [TCC]), CAU 528 consists of Corrective Action Site 25-27-03, Polychlorinated Biphenyls Surface Contamination. Test Cell C was built to support the Nuclear Rocket Development Station (operational between 1959 and 1973) activities including conducting ground tests and static firings of nuclear engine reactors. Although CAU 528 was not considered as a direct potential source of PCBs and petroleum contamination, two potential sources of contamination have nevertheless been identified from an unknown source in concentrations that could potentially pose an unacceptable risk to human health and/or the environment. This CAU's close proximity to TCC prompted Shaw to collect surface soil samples, which have indicated the presence of PCBs extending throughout the area to the north, east, south, and even to the edge of the western boundary. Based on this information, more extensive field investigation activities are being planned, the results of which are to be used to support a defensible evaluation of corrective action alternatives in the corrective action decision document.

U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

2003-05-08T23:59:59.000Z

344

Closure of the Fast Flux Test Facility: Current Status and Future Plans  

SciTech Connect (OSTI)

The Fast Flux Test Facility (FFTF) was a 400 MWt sodium cooled fast reactor designed and constructed in the 1970's. The original purpose of the facility was to develop and test advanced fuels and materials for the liquid metal fast breeder reactor program. The facility operated very successfully from 1982 through 1992, fulfilling its original mission as well as other identified missions. However, in 1993 the Department of Energy concluded that there was no longer a need for the FFTF and thus ordered that it be shut down. Following eight years of additional study of potential new missions, the final decision to shut down the facility was made in 2001. (During this eight year period the plant was maintained in a condition to allow safe and efficient shut down or restart). The complete closure of the FFTF consists of the following phases: - Deactivation - removal/stabilization of hazards to allow long-term storage (2001-2009); - Surveillance and maintenance - minimum cost compliant storage (2010-2015); - Decontamination and decommissioning (2016-2024). All of the FFTF fuel has been removed from the site except the sodium-bonded fuel that is destined for transportation to Idaho National Laboratory for final disposition. The sodium-bonded fuel had metallic sodium inside of the fuel pin to increase the heat transfer from the fuel pellet to the clad in order to reduce pellet centerline temperature. Three hundred and seventy-six (376) fuel assemblies have been washed (sodium removed) and transferred to storage at other Hanford locations. The majority of the spent fuel is stored in interim storage casks designed for a 50 year storage life, holding seven assemblies each. All sodium systems have been drained and the sodium stored under an inert gas blanket at ambient temperature in a Sodium Storage Facility at the FFTF site. This facility consists of four large tanks and associated piping. The main contaminants are sodium-22, cesium-137 and tritium. The sodium-potassium (NaK) that was used as an intermediate cooling fluid in several FFTF systems has been drained and removed or flushed to sodium systems where it became mixed with the sodium. The in-containment hot cell has minimal sodium contamination, is currently inerted with argon and is being used for loading of the T-3 transportation cask with the sodium-bonded fuel for transportation to Idaho National Laboratory. The majority of the fuel handling machines are still operational and being used for loading the sodium-bonded fuel into the T-3 casks. This equipment will be shut down immediately following completion of shipment of the sodium-bonded fuel. The majority of hotel systems are still operating. Four of the eight 400-ton chillers have been shut down and four of the cooling towers have been shut down. The argon system is operational and supplying gas for sodium systems cover gas, in-containment hot cell atmosphere and fuel handling systems. The nitrogen system remains in service supplying cover gas to the demineralized water system and fire suppression systems. Eleven of the facilities nineteen transformers containing polychlorinated biphenyls (PCBs) have been removed and significant re-routing of power has been performed to support the long term minimum cost surveillance mode. Future plans include the complete deactivation, the long-term surveillance and maintenance, the sodium disposition and the decontamination and decommissioning The most complex and costly activity during the decontamination and decommissioning phase will be the removal of the 'residual sodium' in the sodium systems. It was impractical to remove the residual sodium during the systems draining evolution. It is estimated that approximately 24,000 liters (6,400 gallons) remain within the systems. The complexity of design of the FFTF exceeds any sodium facility in the United States in which sodium removal has occurred. There are a total of 21 miles of sodium piping in the FFTF as well as three large vessels (the reactor vessel and two spent fuel pool vessels) that will require partial disassembly and drilli

Farabee, O.A. [US Department of Energy, PO Box 550, Richland, WA 99352 (United States); Witherspoon, W.V. [Fluor Hanford, PO Box 1000 N2-51, Richland, WA 99352 (United States)

2008-01-15T23:59:59.000Z

345

Generation IV Reactors Integrated Materials Technology Program Plan: Focus on Very High Temperature Reactor Materials  

SciTech Connect (OSTI)

Since 2002, the Department of Energy's (DOE's) Generation IV Nuclear Energy Systems (Gen IV) Program has addressed the research and development (R&D) necessary to support next-generation nuclear energy systems. The six most promising systems identified for next-generation nuclear energy are described within this roadmap. Two employ a thermal neutron spectrum with coolants and temperatures that enable hydrogen or electricity production with high efficiency (the Supercritical Water Reactor-SCWR and the Very High Temperature Reactor-VHTR). Three employ a fast neutron spectrum to enable more effective management of actinides through recycling of most components in the discharged fuel (the Gas-cooled Fast Reactor-GFR, the Lead-cooled Fast Reactor-LFR, and the Sodium-cooled Fast Reactor-SFR). The Molten Salt Reactor (MSR) employs a circulating liquid fuel mixture that offers considerable flexibility for recycling actinides and may provide an alternative to accelerator-driven systems. At the inception of DOE's Gen IV program, it was decided to significantly pursue five of the six concepts identified in the Gen IV roadmap to determine which of them was most appropriate to meet the needs of future U.S. nuclear power generation. In particular, evaluation of the highly efficient thermal SCWR and VHTR reactors was initiated primarily for energy production, and evaluation of the three fast reactor concepts, SFR, LFR, and GFR, was begun to assess viability for both energy production and their potential contribution to closing the fuel cycle. Within the Gen IV Program itself, only the VHTR class of reactors was selected for continued development. Hence, this document will address the multiple activities under the Gen IV program that contribute to the development of the VHTR. A few major technologies have been recognized by DOE as necessary to enable the deployment of the next generation of advanced nuclear reactors, including the development and qualification of the structural materials needed to ensure their safe and reliable operation. The focus of this document will be the overall range of DOE's structural materials research activities being conducted to support VHTR development. By far, the largest portion of material's R&D supporting VHTR development is that being performed directly as part of the Next-Generation Nuclear Plant (NGNP) Project. Supplementary VHTR materials R&D being performed in the DOE program, including university and international research programs and that being performed under direct contracts with the American Society for Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, will also be described. Specific areas of high-priority materials research that will be needed to deploy the NGNP and provide a basis for subsequent VHTRs are described, including the following: (1) Graphite: (a) Extensive unirradiated materials characterization and assessment of irradiation effects on properties must be performed to qualify new grades of graphite for nuclear service, including thermo-physical and mechanical properties and their changes, statistical variations from billot-to-billot and lot-to-lot, creep, and especially, irradiation creep. (b) Predictive models, as well as codification of the requirements and design methods for graphite core supports, must be developed to provide a basis for licensing. (2) Ceramics: Both fibrous and load-bearing ceramics must be qualified for environmental and radiation service as insulating materials. (3) Ceramic Composites: Carbon-carbon and SiC-SiC composites must be qualified for specialized usage in selected high-temperature components, such as core stabilizers, control rods, and insulating covers and ducting. This will require development of component-specific designs and fabrication processes, materials characterization, assessment of environmental and irradiation effects, and establishment of codes and standards for materials testing and design requirements. (4) Pressure Vessel Steels: (a) Qualification of short-term, high-temperature properties of light water rea

Corwin, William R [ORNL; Burchell, Timothy D [ORNL; Katoh, Yutai [ORNL; McGreevy, Timothy E [ORNL; Nanstad, Randy K [ORNL; Ren, Weiju [ORNL; Snead, Lance Lewis [ORNL; Wilson, Dane F [ORNL

2008-08-01T23:59:59.000Z

346

Test plan for the pilot cell test of inert anodes: Report on the June 1991 meeting at the Reynolds Metals Company facility  

SciTech Connect (OSTI)

The Inert Electrodes Program at the Pacific Northwest Laboratory (PNL) is supported by the Office of Industrial Processes (OIP) of the US Department of Energy (DOE) and is aimed at improving the energy efficiency of Hall-Heroult cells through the development of inert anodes. The inert anodes currently under study are composed of a cermet material of the general composition NiO-NiFe{sub 2}O{sub 4}-Cu. The program has three primary objectives: (1) evaluate the anode material in a pilot cell facility, (2) investigate the mechanisms of the electrochemical reactions at the anodes surface, and (3) develop sensors for monitoring various anode and/or electrolyte conditions. This report discusses a test plan that has been developed for the pilot cell test of the inert anodes. 6 refs., 7 figs., 4 tabs.

Windisch, C.F. Jr. (Pacific Northwest Lab., Richland, WA (United States)); Alcorn, T.R.; Tabereaux, A.T. (Reynolds Metals Co., Muscle Shoals, AL (United States). Mfg. Technology Lab.)

1991-09-01T23:59:59.000Z

347

Use of Frequency Response Metrics to Assess the Planning and Operating Requirements for Reliable Integration of Variable Renewable Generation  

E-Print Network [OSTI]

2007. Integration of Renewable Resources. Transmissionfor integrating renewable resources on the California ISO-assess the level of renewable resources that can be reliably

Eto, Joseph H.

2011-01-01T23:59:59.000Z

348

CORRECTIVE ACTION PLAN FOR CORRECTIVE ACTION UNIT 536: AREA 3 RELEASE SITE, NEVADA TEST SITE, NEVADA  

SciTech Connect (OSTI)

CAU 536 consists of CAS 03-44-02, Steam Jenny Discharge, located in Area 3 of the NTS. The site was characterized in 2004 according to the approved CAIP and the site characterization results are reported in the CAU 536 CADD. The purpose of this Corrective Action Plan (CAP) is to provide the detailed scope of work required to implement the recommended corrective actions as specified in the approved CAU 536 CADD.

NONE

2005-09-01T23:59:59.000Z

349

Record of Technical Change for Corrective Action Plan for Corrective Action Unit 140: Waste Dumps, burn Pits, and Storage Area, Nevada Test Site, Nevada  

SciTech Connect (OSTI)

Record of Technical Change for Corrective Action Plan for Corrective Action Unit 140: Waste Dumps, Burn Pits, and Storage Area, Nevada Test Site, Nevada (DOE/NV--963-Rev 2, dated November 2004).

U.S. Department of Energy, National Nuclear Security Administration, Nevada Site Office; Bechtel Nevada

2005-01-05T23:59:59.000Z

350

Global nuclear energy partnership fuels transient testing at the Sandia National Laboratories nuclear facilities : planning and facility infrastructure options.  

SciTech Connect (OSTI)

The Global Nuclear Energy Partnership fuels development program is currently developing metallic, oxide, and nitride fuel forms as candidate fuels for an Advanced Burner Reactor. The Advance Burner Reactor is being designed to fission actinides efficiently, thereby reducing the long-term storage requirements for spent fuel repositories. Small fuel samples are being fabricated and evaluated with different transuranic loadings and with extensive burnup using the Advanced Test Reactor. During the next several years, numerous fuel samples will be fabricated, evaluated, and tested, with the eventual goal of developing a transmuter fuel database that supports the down selection to the most suitable fuel type. To provide a comparative database of safety margins for the range of potential transmuter fuels, this report describes a plan to conduct a set of early transient tests in the Annular Core Research Reactor at Sandia National Laboratories. The Annular Core Research Reactor is uniquely qualified to perform these types of tests because of its wide range of operating capabilities and large dry central cavity which extents through the center of the core. The goal of the fuels testing program is to demonstrate that the design and fabrication processes are of sufficient quality that the fuel will not fail at its design limit--up to a specified burnup, power density, and operating temperature. Transient testing is required to determine the fuel pin failure thresholds and to demonstrate that adequate fuel failure margins exist during the postulated design basis accidents.

Kelly, John E.; Wright, Steven Alan; Tikare, Veena; MacLean, Heather J. (Idaho National Laboratory, Idaho Falls, ID); Parma, Edward J., Jr.; Peters, Curtis D.; Vernon, Milton E.; Pickard, Paul S.

2007-10-01T23:59:59.000Z

351

Test Plan: Phase 1 demonstration of 3-phase electric arc melting furnace technology for vitrifying high-sodium content low-level radioactive liquid wastes  

SciTech Connect (OSTI)

This document provides a test plan for the conduct of electric arc vitrification testing by a vendor in support of the Hanford Tank Waste Remediation System (TWRS) Low-Level Waste (LLW) Vitrification Program. The vendor providing this test plan and conducting the work detailed within it [one of seven selected for glass melter testing under Purchase Order MMI-SVV-384216] is the US Bureau of Mines, Department of the Interior, Albany Research Center, Albany, Oregon. This test plan is for Phase I activities described in the above Purchase Order. Test conduct includes feed preparation activities and melting of glass with Hanford LLW Double-Shell Slurry Feed waste simulant in a 3-phase electric arc (carbon electrode) furnace.

Eaton, W.C. [ed.

1995-05-31T23:59:59.000Z

352

Project W-314 specific test and evaluation plan for transfer line SN-633 (241-AX-B to 241-AY-02A)  

SciTech Connect (OSTI)

The purpose of this Specific Test and Evaluation Plan (STEP) is to provide a detailed written plan for the systematic testing of modifications made by the addition of the SN-633 transfer line by the W-314 Project. The STEP develops the outline for test procedures that verify the system`s performance to the established Project design criteria. The STEP is a lower tier document based on the W-314 Test and Evaluation Plan (TEP). This STEP encompasses all testing activities required to demonstrate compliance to the project design criteria as it relates to the addition of transfer line SN-633. The Project Design Specifications (PDS) identify the specific testing activities required for the Project. Testing includes Validations and Verifications (e.g., Commercial Grade Item Dedication activities), Factory Acceptance Tests (FATs), installation tests and inspections, Construction Acceptance Tests (CATs), Acceptance Test Procedures (ATPs), Pre-Operational Test Procedures (POTPs), and Operational Test Procedures (OTPs). It should be noted that POTPs are not required for testing of the transfer line addition. The STEP will be utilized in conjunction with the TEP for verification and validation.

Hays, W.H.

1998-03-20T23:59:59.000Z

353

Evaluation of Maxim Module-Integrated Electronics at the DOE Regional Test Centers: Preprint  

SciTech Connect (OSTI)

Module-embedded power electronics developed by Maxim Integrated are under evaluation through a partnership with the Department of Energy's Regional Test Center (RTC) program. Field deployments of both conventional modules and electronics-enhanced modules are designed to quantify the performance advantage of Maxim's products under different amounts of inter-row shading, and their ability to be deployed at a greater ground-coverage-ratio than conventional modules. Simulations in PVSYST have quantified the predicted performance difference between conventional modules and Maxim's modules from inter-row shading. Initial performance results have identified diffuse irradiance losses at tighter row spacing for both the Maxim and conventional modules. Comparisons with published models show good agreement with models predicting the greatest diffuse irradiance losses. At tighter row spacing, all of the strings equipped with embedded power electronics outperformed their conventional peers. An even greater performance advantage is predicted to occur in the winter months when the amount of inter-row shading mismatch is at a maximum.

Deline, C.; Sekulic, B.; Stein, J.; Barkaszi, S.; Yang, J.; Kahn, S.

2014-07-01T23:59:59.000Z

354

Liquid Effluent Monitoring Information System test plans releases 2.0 and 3.0  

SciTech Connect (OSTI)

The Liquid Effluent Monitoring Information System (LEMIS) is being developed as the organized information repository facility in support of the liquid effluent monitoring requirements of the Tri-Party Agreement. It is necessary to provide an automated repository into which the results from liquid effluent sampling will be placed. This repository must provide for effective retention, review, and retrieval of selected sample data by authorized persons and organizations. This System Architecture document is the aggregation of the DMR P+ methodology project management deliverables. Together they represent a description of the project and its plan through four Releases, corresponding to the definition and prioritization of requirements defined by the user.

Guettler, D.A.

1995-05-26T23:59:59.000Z

355

Test Plan for Evaluating Hammer and Fixed Cutter Grinders Using Multiple Varieties and Moistures of Biomass Feedstock  

SciTech Connect (OSTI)

Biomass preprocessing is a critical operation in the preparation of feedstock for the front-end of a cellulosic ethanol biorefinery. Its purpose is to chop, grind, or otherwise format the biomass material into a suitable feedstock for optimum conversion to ethanol and other bioproducts. Without this operation, the natural size, bulk density, and flowability characteristics of harvested biomass would decrease the capacities and efficiencies of feedstock assembly unit operations and biorefinery conversion processes to the degree that programmatic cost targets could not be met. The preprocessing unit operation produces a bulk flowable material that 1) improves handling and conveying efficiencies throughout the feedstock assembly system and biorefinery 2) increases biomass surface areas for improved pretreatment efficiencies, 3) reduces particle sizes for improved feedstock uniformity and density, and 4) fractionates structural components for improved compositional quality. The Idaho National Laboratory (INL) is tasked with defining the overall efficiency/effectiveness of current commercial hammer and fixed cutter grinding systems and other connecting systems such as harvest and collection, storage, transportation, and handling for a wide variety of feedstock types used in bioethanol or syngas production. This test plan details tasks and activities for two separate full-scale grinding tests: Material Characterization Test and Machine Characterization Test. For the Material Characterization Test, a small amount (~5-7 tons each) of several feedstock varieties will be ground. This test will define the fractionation characteristics of the grinder that affect the bulk density, particle size distribution, and quality of the size reduced biomass resulting from different separation screen sizes. A specific screen size will be selected based on the characteristics of the ground material. The Machine Characterization Test will then use this selected screen to grind several 30-ton batches of different feedstock varieties and moistures. This test will focus on identifying the performance parameters of the grinding system specific to the feed, fractionation, and screen separation components and their affect on machine capacity and efficiency.

Not listed

2007-07-01T23:59:59.000Z

356

Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 116: Area 25 Test Cell C Facility, Nevada Test Site, Nevada, Revision 1  

SciTech Connect (OSTI)

This Streamlined Approach for Environmental Restoration (SAFER) Plan identifies the activities required for the closure of Corrective Action Unit (CAU) 116, Area 25 Test Cell C Facility. The Test Cell C (TCC) Facility is located in Area 25 of the Nevada Test Site (NTS) approximately 25 miles northwest of Mercury, Nevada (Figure 1). CAU 116 is currently listed in Appendix III of the Federal Facility Agreement and Consent Order (FFACO) of 1996 (as amended February 2008) and consists of two Corrective Action Sites (CASs): (1) CAS 25-23-20, Nuclear Furnace Piping; and (2) CAS 25-41-05, Test Cell C Facility. CAS 25-41-05 is described in the FFACO as the TCC Facility but actually includes Building 3210 and attached concrete shield wall only. CAU 116 will be closed by demolishing Building 3210, the attached concrete shield wall, and the nuclear furnace piping. In addition, as a best management practice (BMP), Building 3211 (moveable shed) will be demolished due to its close proximity to Building 3210. This will aid in demolition and disposal operations. Radiological surveys will be performed on the demolition debris to determine the proper disposal pathway. As much of the demolition debris as space allows will be placed into the Building 3210 basement structure. After filling to capacity with demolition debris, the basement structure will be mounded or capped and closed with administrative controls. Prior to beginning demolition activities and according to an approved Sampling and Analysis Plan (SAP), representative sampling of surface areas that are known, suspected, or have the potential to contain hazardous constituents such as lead or polychlorinated biphenyls (PCBs) will be performed throughout all buildings and structures. Sections 2.3.2, 4.2.2.2, 4.2.2.3, 4.3, and 6.2.6.1 address the methodologies employed that assure the solid debris placed in the basement structure will not contain contaminants of concern (COCs) above hazardous waste levels. The anticipated post-closure-posting requirements for the mounded/capped basement structure, as well as for the entire CAU, are addressed in Section 4.2.10. The site contains radiologically impacted surfaces and hazardous materials. Based on review of the historical information for CAU 116 and recent site inspections, there is sufficient process knowledge to close CAU 116 using the SAFER process. CAUs that may be closed using the SAFER process have conceptual corrective actions that are clearly identified. Consequently, corrective action alternatives can be chosen prior to completing a corrective action investigation, given anticipated investigation results. The SAFER process combines elements of the data quality objective (DQO) process and the observational approach to plan and conduct closure activities. The DQOs are used to identify the problem and define the type and quality of data needed to complete the investigation phase of the SAFER process. The purpose of the investigation phase is to verify the adequacy of existing information used to determine the chosen corrective action. The observational approach provides a framework for managing uncertainty during the planning and decision-making phases of the project. The SAFER process allows for technical decisions to be made based on information gathered during site visits, interviews, meetings, research, and a consensus of opinion by the decontamination and decommissioning (D&D) team members. Any uncertainties are addressed by documented assumptions that are verified by sampling and analysis, data evaluation, onsite observations, and contingency plans, as necessary. Closure activities may proceed simultaneously with site characterization as sufficient data are gathered to confirm or disprove the assumptions made during selection of the corrective action. If, at any time during the closure process, new information is discovered that indicates that closure activities should be revised, closure activities will be reevaluated as appropriate. Based on a detailed review of historical documentation, there is sufficient process know

NSTec Environmental Restoration

2008-12-01T23:59:59.000Z

357

Model-driven Service Integration Testing -A Case Study Sebastian Wieczorek and Alin Stefanescu and Andreas Roth  

E-Print Network [OSTI]

; Service- oriented Architecture; Case Study; Service Choreographies I. INTRODUCTION Service-oriented architectures (SOA) provide frameworks and methods to compose single services in order to realize complexModel-driven Service Integration Testing - A Case Study Sebastian Wieczorek and Alin Stefanescu

Southampton, University of

358

A One System Integrated Approach to Simulant Selection for Hanford High Level Waste Mixing and Sampling Tests  

SciTech Connect (OSTI)

The Hanford Tank Operations Contractor (TOC) and the Hanford Waste Treatment and Immobilization Plant (WTP) contractor are both engaged in demonstrating mixing, sampling, and transfer system capabilities using simulated Hanford High-Level Waste (HLW) formulations. This represents one of the largest remaining technical issues with the high-level waste treatment mission at Hanford. Previous testing has focused on very specific TOC or WTP test objectives and consequently the simulants were narrowly focused on those test needs. A key attribute in the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 2010-2 is to ensure testing is performed with a simulant that represents the broad spectrum of Hanford waste. The One System Integrated Project Team is a new joint TOC and WTP organization intended to ensure technical integration of specific TOC and WTP systems and testing. A new approach to simulant definition has been mutually developed that will meet both TOC and WTP test objectives for the delivery and receipt of HLW. The process used to identify critical simulant characteristics, incorporate lessons learned from previous testing, and identify specific simulant targets that ensure TOC and WTP testing addresses the broad spectrum of Hanford waste characteristics that are important to mixing, sampling, and transfer performance are described.

Thien, Mike G. [Washington River Protection Solutions, LLC, Richland, WA (United States); Barnes, Steve M. [URS, Richland, WA (United States)

2013-01-17T23:59:59.000Z

359

A One System Integrated Approach to Simulant Selection for Hanford High Level Waste Mixing and Sampling Tests - 13342  

SciTech Connect (OSTI)

The Hanford Tank Operations Contractor (TOC) and the Hanford Waste Treatment and Immobilization Plant (WTP) contractor are both engaged in demonstrating mixing, sampling, and transfer system capabilities using simulated Hanford High-Level Waste (HLW) formulations. This represents one of the largest remaining technical issues with the high-level waste treatment mission at Hanford. Previous testing has focused on very specific TOC or WTP test objectives and consequently the simulants were narrowly focused on those test needs. A key attribute in the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 2010-2 is to ensure testing is performed with a simulant that represents the broad spectrum of Hanford waste. The One System Integrated Project Team is a new joint TOC and WTP organization intended to ensure technical integration of specific TOC and WTP systems and testing. A new approach to simulant definition has been mutually developed that will meet both TOC and WTP test objectives for the delivery and receipt of HLW. The process used to identify critical simulant characteristics, incorporate lessons learned from previous testing, and identify specific simulant targets that ensure TOC and WTP testing addresses the broad spectrum of Hanford waste characteristics that are important to mixing, sampling, and transfer performance are described. (authors)

Thien, Mike G. [Washington River Protection Solutions, LLC, P.O Box 850, Richland WA, 99352 (United States)] [Washington River Protection Solutions, LLC, P.O Box 850, Richland WA, 99352 (United States); Barnes, Steve M. [Waste Treatment Plant, 2435 Stevens Center Place, Richland WA 99354 (United States)] [Waste Treatment Plant, 2435 Stevens Center Place, Richland WA 99354 (United States)

2013-07-01T23:59:59.000Z

360

Moving granular-bed filter development program, Option III: Development of moving granular-bed filter technology for multi-contaminant control. Task 14: Test plan; Topical report  

SciTech Connect (OSTI)

An experimental test plan has been prepared for DOE/METC review and approval to develop a filter media suitable for multi-contaminant control in granular-bed filter (GBF) applications. The plan includes identification, development, and demonstration of methods for enhanced media morphology, chemical reactivity, and mechanical strength. The test plan includes media preparation methods, physical and chemical characterization methods for fresh and reacted media, media evaluation criteria, details of test and analytical equipment, and test matrix of the proposed media testing. A filter media composed of agglomerated limestone and clay was determined to be the best candidate for multi-contaminate control in GBF operation. The combined limestone/clay agglomerate has the potential to remove sulfur and alkali species, in addition to particulate, and possibly halogens and trace heavy metals from coal process streams.

Haas, J.C.; Olivo, C.A.; Wilson, K.B.

1994-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "integrated test plan" 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

Designing and testing the neutron source deployment system and calibration plan for a dark matter detector  

E-Print Network [OSTI]

In this thesis, we designed and tested a calibration and deployment system for the MiniCLEAN dark matter detector. The deployment system uses a computer controlled winch to lower a canister containing a neutron source into ...

Westerdale, Shawn (Shawn S.)

2011-01-01T23:59:59.000Z

362

Corrective Action Decision Document/ Corrective Action Plan for Corrective Action Unit 443: Central Nevada Test Area-Subsurface Central Nevada Test Area, Nevada, Rev. No. 0  

SciTech Connect (OSTI)

This Corrective Action Decision Document/Corrective Action Plan (CADD/CAP) has been prepared for the subsurface at the Central Nevada Test Area (CNTA) Corrective Action Unit (CAU) 443, CNTA - Subsurface, Nevada, in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996). CAU 443 is located in Hot Creek Valley in Nye County, Nevada, north of U.S. Highway 6, about 48 kilometers north of Warm Springs, Nevada. The CADD/CAP combines the decision document (CADD) with the corrective action plan (CAP) and provides or references the specific information necessary to recommend corrective actions for the UC-1 Cavity (Corrective Action Site 58-57-001) at CAU 443, as provided in the FFACO. The purpose of the CADD portion of the document (Section 1.0 to Section 4.0) is to identify and provide a rationale for the selection of a recommended corrective action alternative for the subsurface at CNTA. To achieve this, the following tasks were required: (1) Develop corrective action objectives; (2) Identify corrective action alternative screening criteria; (3) Develop corrective action alternatives; (4) Perform detailed and comparative evaluations of the corrective action alternatives in relation to the corrective action objectives and screening criteria; and (5) Recommend a preferred corrective action alternative for the subsurface at CNTA. A Corrective Action Investigation (CAI) was performed in several stages from 1999 to 2003, as set forth in the ''Corrective Action Investigation Plan for the Central Nevada Test Area Subsurface Sites (Corrective Action Unit No. 443)'' (DOE/NV, 1999). Groundwater modeling was the primary activity of the CAI. Three phases of modeling were conducted for the Faultless underground nuclear test. The first involved the gathering and interpretation of geologic and hydrogeologic data into a three-dimensional numerical model of groundwater flow, and use of the output of the flow model for a transport model of radionuclide release and migration behavior (Pohlmann et al., 2000). The second modeling phase (known as a Data Decision Analysis [DDA]) occurred after the Nevada Division of Environmental Protection reviewed the first model and was designed to respond to concerns regarding model uncertainty (Pohll and Mihevc, 2000). The third modeling phase updated the original flow and transport model to incorporate the uncertainty identified in the DDA, and focused the model domain on the region of interest to the transport predictions. This third phase culminated in the calculation of contaminant boundaries for the site (Pohll et al., 2003).

Susan Evans

2004-11-01T23:59:59.000Z

363

Vertical Integration in Gasoline Supply: An Empirical Test of Raising Rivals' Costs  

E-Print Network [OSTI]

Vertical Integration in Gasoline Supply: An Empirical Testfor the reÞning and distribution of gasoline and the whole-sale price of unbranded gasoline sold to independent

Gilbert, Richard; Hastings, Justine

2001-01-01T23:59:59.000Z

364

Vertical Integration in Gasoline Supply: An Empirical Test of Raising Rivals' Costs  

E-Print Network [OSTI]

Vertical Integration in Gasoline Supply: An Empirical Testoligopoly, market power, gasoline Abstract: This paperand distribution of gasoline and the wholesale price of

Gilbert, Richard; Hastings, Justine

2001-01-01T23:59:59.000Z

365

FINAL REPORT INTEGRATED DM1200 MELTER TESTING USING AZ 102 AND C 106/AY-102 HLW SIMULANTS: HLW SIMULANT VERIFICATION VSL-05R5800-1 REV 0 6/27/05  

SciTech Connect (OSTI)

The principal objectives of the DM1200 melter tests were to determine the effects of feed rheology, feed solid content, and bubbler configuration on glass production rate and off-gas system performance while processing the HLW AZ-101 and C-106/AY-102 feed compositions; characterize melter off-gas emissions; characterize the performance of the prototypical off-gas system components, as well as their integrated performance; characterize the feed, glass product, and off-gas effluents; and perform pre- and post test inspections of system components. The specific objectives (including test success criteria) of this testing, along with how each objective was met, are outlined in a table. The data provided in this Final Report address the impacts of HLW melter feed rheology on melter throughput and validation of the simulated HLW melter feeds. The primary purpose of this testing is to further validate/verify the HLW melter simulants that have been used for previous melter testing and to support their continued use in developing melter and off-gas related processing information for the Project. The primary simulant property in question is rheology. Simulants and melter feeds used in all previous melter tests were produced by direct addition of chemicals; these feed tend to be less viscous than rheological the upper-bound feeds made from actual wastes. Data provided here compare melter processing for the melter feed used in all previous DM100 and DM1200 tests (nominal melter feed) with feed adjusted by the feed vendor (NOAH Technologies) to be more viscous, thereby simulating more closely the upperbounding feed produced from actual waste. This report provides results of tests that are described in the Test Plan for this work. The Test Plan is responsive to one of several test objectives covered in the WTP Test Specification for this work; consequently, only part of the scope described in the Test Specification was addressed in this particular Test Plan. For the purpose of comparison, the tests reported here were performed with AZ-102 and C-106/AY-102 HLW simulants and glass compositions that are essentially the same as those used for recent DM1200 tests. One exception was the use of an alternate, higher-waste-loading C-106/AY-102 glass composition that was used in previous DM100 tests to further evaluate the performance of the optimized bubbler configuration.

KRUGER AA; MATLACK KS; GONG W; BARDAKCI T; D'ANGELO NA; BRANDYS M; KOT WK; PEGG IL

2011-12-29T23:59:59.000Z

366

Nevada Test Site site treatment plan, final annual update. Revision 1  

SciTech Connect (OSTI)

A Site Treatment Plan (STP) is required for facilities at which the US Department of Energy Nevada Operations Office (DOE/NV) generates or stores mixed waste (MW), defined by the Federal Facility Compliance Act (FFCAct) as waste containing both a hazardous waste subject to the Resource Conservation and Recovery Act (RCRA) and a radioactive material subject to the Atomic Energy Act. This STP was written to identify specific treatment facilities for treating DOE/NV generated MW and provides proposed implementation schedules. This STP was approved by the Nevada Division of Environmental Protection (NDEP) and provided the basis for the negotiation and issuance of the FFCAct Consent Order (CO) dated March 6, 1996. The FFCAct CO sets forth stringent regulatory requirements to comply with the implementation of the STP.

NONE

1998-04-01T23:59:59.000Z

367

Demonstration testing and evaluation of in situ soil heating. Health and safety plan (Revision 2)  

SciTech Connect (OSTI)

This document is the Health and Safety Plan (HASP) for the demonstration of IITRI`s EM Treatment Technology. In this process, soil is heated in situ by means of electrical energy for the removal of hazardous organic contaminants. This process will be demonstrated on a small plot of contaminated soil located in the Pit Area of Classified Burial Ground K-1070-D, K-25 Site, Oak Ridge, TN. The purpose of the demonstration is to remove organic contaminants present in the soil by heating to a temperature range of 85{degrees} to 95{degrees}C. The soil will be heated in situ by applying 60-Hz AC power to an array of electrodes placed in boreholes drilled through the soil. In this section a brief description of the process is given along with a description of the site and a listing of the contaminants found in the area.

Dev, H.

1994-12-28T23:59:59.000Z

368

Energy Smart Schools--Applied Research, Field Testing, and Technology Integration  

SciTech Connect (OSTI)

The National Association of State Energy Officials (NASEO) in conjunction with the California Energy Commission, the Energy Center of Wisconsin, the Florida Solar Energy Center, the New York State Energy Research and Development Authority, and the Ohio Department of Development's Office of Energy Efficiency conducted a four-year, cost-share project with the U.S. Department of Energy (USDOE), Office of Energy Efficiency and Renewable Energy to focus on energy efficiency and high-performance technologies in our nation's schools. NASEO was the program lead for the MOU-State Schools Working group, established in conjunction with the USDOE Memorandum of Understanding process for collaboration among state and federal energy research and demonstration offices and organizations. The MOU-State Schools Working Group included State Energy Offices and other state energy research organizations from all regions of the country. Through surveys and analyses, the Working Group determined the school-related energy priorities of the states and established a set of tasks to be accomplished, including the installation and evaluation of microturbines, advanced daylighting research, testing of schools and classrooms, and integrated school building technologies. The Energy Smart Schools project resulted in the adoption of advanced energy efficiency technologies in both the renovation of existing schools and building of new ones; the education of school administrators, architects, engineers, and manufacturers nationwide about the energy-saving, economic, and environmental benefits of energy efficiency technologies; and improved the learning environment for the nation's students through use of better temperature controls, improvements in air quality, and increased daylighting in classrooms. It also provided an opportunity for states to share and replicate successful projects to increase their energy efficiency while at the same time driving down their energy costs.

Nebiat Solomon; Robin Vieira; William L. Manz; Abby Vogen; Claudia Orlando; Kimberlie A. Schryer

2004-12-01T23:59:59.000Z

369

The ATLAS Liquid Argon Calorimeter Construction, Integration, Commissioning and Performance from Selected Particle Beam Test Results  

E-Print Network [OSTI]

­Construction of the ATLAS liquid argon calorimeter is now complete and integration with the ATLAS detector in the cavern with the move of the barrel cryostat to the ATLAS cavern. Since then, integration of the endcap calorimeters, waiting to be lowered into the cavern. The other will be moved to Point 1 by late 2005 / early 2006

Krieger, Peter

370

Corrective Action Investigation Plan for Corrective Action Unit 543: Liquid Disposal Units, Nevada Test Site, Nevada: Revision 0  

SciTech Connect (OSTI)

The general purpose of this Corrective Action Investigation Plan is to ensure that adequate data are collected to provide sufficient and reliable information to identify, evaluate, and select technically viable corrective action alternatives (CAAs) for Corrective Action Unit (CAU) 543: Liquid Disposal Units, Nevada Test Site (NTS), Nevada. Located in Areas 6 and 15 on the NTS, CAU 543 is comprised of a total of seven corrective action sites (CASs), one in Area 6 and six in Area 15. The CAS in Area 6 consists of a Decontamination Facility and its components which are associated with decontamination of equipment, vehicles, and materials related to nuclear testing. The six CASs in Area 15 are located at the U.S. Environmental Protection Agency Farm and are related to waste disposal activities at the farm. Sources of possible contamination at Area 6 include potentially contaminated process waste effluent discharged through a process waste system, a sanitary waste stream generated within buildings of the Decon Facility, and radiologically contaminated materials stored within a portion of the facility yard. At Area 15, sources of potential contamination are associated with the dairy operations and the animal tests and experiments involving radionuclide uptake. Identified contaminants of potential concern include volatile organic compounds, semivolatile organic compounds, petroleum hydrocarbons, pesticides, herbicides, polychlorinated biphenyls, metals, and radionuclides. Three corrective action closure alternatives - No Further Action, Close in Place, or Clean Closure - will be recommended for CAU 543 based on an evaluation of all the data quality objective-related data. Field work will be conducted following approval of the plan. The results of the field investigation will support a defensible evaluation of CAAs that will be presented in the Corrective Action Decision Document.

U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

2004-05-03T23:59:59.000Z

371

Corrective Action Investigation Plan for Corrective Action Unit 375: Area 30 Buggy Unit Craters, Nevada Test Site, Nevada  

SciTech Connect (OSTI)

Corrective Action Unit (CAU) 375 is located in Areas 25 and 30 of the Nevada Test Site, which is approximately 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 375 comprises the two corrective action sites (CASs) listed below: • 25-23-22, Contaminated Soils Site • 30-45-01, U-30a, b, c, d, e Craters Existing information on the nature and extent of potential contamination present at the CAU 375 CASs is insufficient to evaluate and recommend corrective action alternatives (CAAs). This document details an investigation plan that will provide for the gathering of sufficient information to evaluate and recommend CAAs. Corrective Action Site 25-23-22 is composed of the releases associated with nuclear rocket testing at Test Cell A (TCA). Test Cell A was used to test and develop nuclear rocket motors as part of the Nuclear Rocket Development Station from its construction in 1958 until 1966, when rocket testing began being conducted at Test Cell C. The rocket motors were built with an unshielded nuclear reactor that produced as much as 1,100 kilowatts (at full power) to heat liquid hydrogen to 4,000 degrees Fahrenheit, at which time the expanded gases were focused out a nozzle to produce thrust. The fuel rods in the reactor were not clad and were designed to release fission fragments to the atmosphere, but due to vibrations and loss of cooling during some operational tests, fuel fragments in excess of planned releases became entrained in the exhaust and spread in the immediate surrounding area. Cleanup efforts have been undertaken at times to collect the fuel rod fragments and other contamination. Previous environmental investigations in the TCA area have resulted in the creation of a number of use restrictions. The industrial area of TCA is encompassed by a fence and is currently posted as a radioactive material area. Corrective Action Site 30-45-01 (releases associated with the Buggy Plowshare test) is located in Area 30 on Chukar Mesa. It was a Plowshare test where five nuclear devices were buried 140 feet (ft) deep in a row at 150-ft intervals. These devices were detonated on March 12, 1968, to produce a trench 254 ft wide, 865 ft long, and 70 ft deep. The mesa where the test was conducted is surrounded on three sides by ravines, and the entire end of the mesa is fenced and posted as a contamination area. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend CAAs. Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on December 2, 2009, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 375.

Patrick Matthews

2010-03-01T23:59:59.000Z

372

Distribution Grid Integration  

Broader source: Energy.gov [DOE]

The DOE Systems Integration team funds distribution grid integration research and development (R&D) activities to address the technical issues that surround distribution grid planning,...

373

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

SciTech Connect (OSTI)

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

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

2013-05-31T23:59:59.000Z

374

Treatability Test Plan for 300 Area Uranium Stabilization through Polyphosphate Injection  

SciTech Connect (OSTI)

The U.S. Department of Energy has initiated a study into possible options for stabilizing uranium at the 300 Area using polyphosphate injection. As part of this effort, PNNL will perform bench- and field-scale treatability testing designed to evaluate the efficacy of using polyphosphate injections to reduced uranium concentrations in the groundwater to meet drinking water standards (30 ug/L) in situ. This technology works by forming phosphate minerals (autunite and apatite) in the aquifer that directly sequester the existing aqueous uranium in autunite minerals and precipitates apatite minerals for sorption and long term treatment of uranium migrating into the treatment zone, thus reducing current and future aqueous uranium concentrations. Polyphosphate injection was selected for testing based on technology screening as part of the 300-FF-5 Phase III Feasibility Study for treatment of uranium in the 300-Area.

Vermeul, Vincent R.; Williams, Mark D.; Fritz, Brad G.; Mackley, Rob D.; Mendoza, Donaldo P.; Newcomer, Darrell R.; Rockhold, Mark L.; Williams, Bruce A.; Wellman, Dawn M.

2007-06-01T23:59:59.000Z

375

Software Testing Jos de Kloe,  

E-Print Network [OSTI]

/GUI interfaces) Integration tests: automatisch verzenden van files naar ECMWF triggeren van processen bij ECMWF Document SVVP=Software Validation and Verification Plan #12;MMM, J. de Kloe, 2 maart 2009 7 GSOV testing Werking van algorithmes Werking van allerhande scripts Complete processor Controleer ook dat foutieve

Stoffelen, Ad

376

Corrective action investigation plan for Corrective Action Unit 340, Pesticide Release Sites, Nevada Test Site, Nye County, Nevada  

SciTech Connect (OSTI)

This Correction Action Investigation Plan (CAIP) has been developed in accordance with the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the US Department of Energy, Nevada Operations Office (DOE/NV); the State of Nevada Division of Environmental Protection (NDEP); and the US Department of Defense. As required by the FFACO (1996), this document provides or references all of the specific information for planning investigation activities associated with three Corrective Action Sites (CASs) located at the Nevada Test Site (NTS). These CASs are collectively known as Corrective Action Unit (CAU) 340, Pesticide Release Sites. According to the FFACO, CASs are sites that may require corrective action(s) and may include solid waste management units or individual disposal or release sites. These sites are CAS 23-21-01, Area 23 Quonset Hut 800 (Q800) Pesticide Release Ditch; CAS 23-18-03, Area 23 Skid Huts Pesticide Storage; and CAS 15-18-02, Area 15 Quonset Hut 15-11 Pesticide Storage (Q15-11). The purpose of this CAIP for CAU 340 is to direct and guide the investigation for the evaluation of the nature and extent of pesticides, herbicides, and other contaminants of potential concern (COPCs) that were stored, mixed, and/or disposed of at each of the CASs.

NONE

1998-01-01T23:59:59.000Z

377

Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 107: Low Impact Soil Sites, Nevada Test Site, Nevada  

SciTech Connect (OSTI)

This Streamlined Approach for Environmental Restoration Plan covers activities associated with Corrective Action Unit (CAU) 107 of the Federal Facility Agreement and Consent Order (FFACO, 1996 [as amended February 2008]). CAU 107 consists of the following Corrective Action Sites (CASs) located in Areas 1, 2, 3, 4, 5, 9, 10, and 18 of the Nevada Test Site. (1) CAS 01-23-02, Atmospheric Test Site - High Alt; (2) CAS 02-23-02, Contaminated Areas (2); (3) CAS 02-23-03, Contaminated Berm; (4) CAS 02-23-10, Gourd-Amber Contamination Area; (5) CAS 02-23-11, Sappho Contamination Area; (6) CAS 02-23-12, Scuttle Contamination Area; (7) CAS 03-23-24, Seaweed B Contamination Area; (8) CAS 03-23-27, Adze Contamination Area; (9) CAS 03-23-28, Manzanas Contamination Area; (10) CAS 03-23-29, Truchas-Chamisal Contamination Area; (11) CAS 04-23-02, Atmospheric Test Site T4-a; (12) CAS 05-23-06, Atmospheric Test Site; (13) CAS 09-23-06, Mound of Contaminated Soil; (14) CAS 10-23-04, Atmospheric Test Site M-10; and (15) CAS 18-23-02, U-18d Crater (Sulky). Based on historical documentation, personnel interviews, site process knowledge, site visits, photographs, engineering drawings, field screening, analytical results, and the results of data quality objectives process (Section 3.0), closure in place with administrative controls or no further action will be implemented for CAU 107. CAU 107 closure activities will consist of verifying that the current postings required under Title 10 Code of Federal Regulations (CFR) Part 835 are in place and implementing use restrictions (URs) at two sites, CAS 03-23-29 and CAS 18-23-02. The current radiological postings combined with the URs are adequate administrative controls to limit site access and worker dose.

NSTec Environmental Restoration

2008-09-30T23:59:59.000Z

378

Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 107: Low Impact Soil Sites, Nevada Test Site, Nevada  

SciTech Connect (OSTI)

This Streamlined Approach for Environmental Restoration Plan covers activities associated with Corrective Action Unit (CAU) 107 of the Federal Facility Agreement and Consent Order (1996 [as amended February 2008]). CAU 107 consists of the following Corrective Action Sites (CASs) located in Areas 1, 2, 3, 4, 5, 9, 10, and 18 of the Nevada Test Site. {sm_bullet} CAS 01-23-02, Atmospheric Test Site - High Alt{sm_bullet} CAS 02-23-02, Contaminated Areas (2){sm_bullet} CAS 02-23-03, Contaminated Berm{sm_bullet} CAS 02-23-10, Gourd-Amber Contamination Area{sm_bullet} CAS 02-23-11, Sappho Contamination Area{sm_bullet} CAS 02-23-12, Scuttle Contamination Area{sm_bullet} CAS 03-23-24, Seaweed B Contamination Area{sm_bullet} CAS 03-23-27, Adze Contamination Area{sm_bullet} CAS 03-23-28, Manzanas Contamination Area{sm_bullet} CAS 03-23-29, Truchas-Chamisal Contamination Area{sm_bullet} CAS 04-23-02, Atmospheric Test Site T4-a{sm_bullet} CAS 05-23-06, Atmospheric Test Site{sm_bullet} CAS 09-23-06, Mound of Contaminated Soil{sm_bullet} CAS 10-23-04, Atmospheric Test Site M-10{sm_bullet} CAS 18-23-02, U-18d Crater (Sulky) Based on historical documentation, personnel interviews, site process knowledge, site visits, photographs, engineering drawings, field screening, analytical results, and the results of data quality objectives process (Section 3.0), closure in place with administrative controls or no further action will be implemented for CAU 107.

NSTec Environmental Restoration

2009-03-31T23:59:59.000Z

379

Recovery Efficiency Test Project: Phase 1, Activity report. Volume 1: Site selection, drill plan preparation, drilling, logging, and coring operations  

SciTech Connect (OSTI)

The recovery Efficiency Test well project addressed a number of technical issues. The primary objective was to determine the increased efficiency gas recovery of a long horizontal wellbore over that of a vertical wellbore and, more specifically, what improvements can be expected from inducing multiple hydraulic fractures from such a wellbore. BDM corporation located, planned, and drilled a long radius turn horizontal well in the Devonian shale Lower Huron section in Wayne County, West Virginia, demonstrating that state-of-the-art technology is capable of drilling such wells. BDM successfully tested drilling, coring, and logging in a horizontal well using air as the circulating medium; conducted reservoir modeling studies to protect flow rates and reserves in advance of drilling operations; observed two phase flow conditions in the wellbore not observed previously; cored a fracture zone which produced gas; observed that fractures in the core and the wellbore were not systematically spaced (varied from 5 to 68 feet in different parts of the wellbore); observed that highest gas show rates reported by the mud logger corresponded to zone with lowest fracture spacing (five feet) or high fracture frequency. Four and one-half inch casting was successfully installed in the borehole and was equipped to isolate the horizontal section into eight (8) zones for future testing and stimulation operations. 6 refs., 48 figs., 10 tabs.

Overbey, W.K. Jr.; Carden, R.S.; Kirr, J.N.

1987-04-01T23:59:59.000Z

380

Dry Coal Feed System and Multi-Element Injector Test Plan  

SciTech Connect (OSTI)

Pratt & Whitney Rocketdyne (PWR) has developed an innovative gasifier concept that uses rocket engine technology to significantly improve gasifier performance, life, and cost compared to current state-of-the-art systems. One key feature of the PWR concept is the use of an ultra-dense phase feed system to provide dry coal to the multi-element injector. This report describes the layout, test procedures, instrumentation and data acquisition requirements for an ultradense phase multi-element injector and feed system to be operated at the University of North Dakota Energy and Environmental Research Center (UNDEERC).

Ken Sprouse; Fred Widman; Alan Darby

2006-08-30T23:59:59.000Z

Note: This page contains sample records for the topic "integrated test plan" 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

New Pump and Treat Facility Remedial Action Work Plan For Test Area North Final Groundwater Remediation, Operable Unit 1-07B  

SciTech Connect (OSTI)

This remedial action work plan identifies the approach and requirements for implementing the medial zone remedial action for Test Area North, Operable Unit 1-07B, at the Idaho National Laboratory. This plan details the management approach for the construction and operation of the New Pump and Treat Facility (NPTF). As identified in the remediatial design/remedial action scope of work, a separate remedial design/remedial action work plan will be prepared for each remedial component of the Operable Unit 1-07B remedial action.

Nelson, L. O.

2007-06-12T23:59:59.000Z

382

Integration and testing of FTS-2: an imaging Fourier transform spectrometer for SCUBA-2  

E-Print Network [OSTI]

the final construction phase. The optical design of the interferometer and modeled performance is presented resolution ranging from resolving powers of R ~10 to 5000. Details of the instrument design, optical modeling, data reduction pipeline and calibration plan which have changed since the project CDR are discussed

Naylor, David A.

383

Report of independent consultants reviewing Integrated Test Stands (ITS) performance and readiness of DARHT for construction start  

SciTech Connect (OSTI)

Independent consultants met at Los Alamos, June 15 and 16, 1993, to review progress on the commissioning of the Integrated Test Stand (ITS) for DARHT and to provide DOE with technical input on readiness for construction of the first radiographic arm of DARHT. The consultants concluded that all milestones necessary for demonstrating the performance of the DARHT accelerator have been met and that the project is ready for construction to resume. The experimental program using ITS should be continued to quantify the comparison of experiment and theory, to test improvements on the injector insulator, and to better evaluate the interaction of the beam and the target.

Not Available

1993-08-01T23:59:59.000Z

384

Dynamic system characterization of an integral test facility of an advanced PWR  

E-Print Network [OSTI]

This work characterizes the dynamic behavior for the modified Large Scale Test Facility (LSTF), which has been selected by the U.S. Nuclear Regulatory Commission for confirmatory testing of the Westinghouse AP600 design. The LSTF is performing a...

Smith, Simon Gregory

1995-01-01T23:59:59.000Z

385

Mixed-use at the landscape scale : integrating agriculture and water management as a case study for interdisciplinary planning  

E-Print Network [OSTI]

Mixed-use planning is now a standard practice in city design and development. It is believed to support diverse and mutually reinforcing elements within a neighborhood. Agricultural landscapes present an analogous opportunity ...

Horne, Christopher (Christopher John)

2010-01-01T23:59:59.000Z

386

California Energy Commission Public Interest EnergyResearch/Energy System Integration -- Transmission-Planning Research&Development Scoping Project  

SciTech Connect (OSTI)

The objective of this Public Interest Energy Research (PIER)scoping project is to identify options for public-interest research and development (R&D) to improve transmission-planning tools, techniques, and methods. The information presented was gathered through a review of current California utility, California Independent System Operator (ISO), and related western states electricity transmission-planning activities and emerging needs. This report presents the project teams findings organized under six topic areas and identifies 17 distinct R&D activities to improve transmission-planning in California and the West. The findings in this report are intended for use, along with other materials, by PIER staff, to facilitate discussions with stakeholders that will ultimately lead to development of a portfolio of transmission-planning R&D activities for the PIER program.

Eto, Joseph H.; Lesieutre, Bernard; Widergren, Steven

2004-07-01T23:59:59.000Z

387

CLOSURE OF THE FAST FLUX TEST FACILITY (FFTF) HISTORY & STATUS & FUTURE PLANS  

SciTech Connect (OSTI)

In 1993, the US Department of Energy (DOE) decided to shut down the Fast Flux Test Facility (FFTF) due to lack of national missions that justified the annual operating budget of approximately $88M/year. The initial vision was to ''deactive'' the facility to an industrially and radiologically safe condition to allow long-term, minimal surveillance storage until approximately 2045. This approach would minimize near term cash flow and allow the radioactive decay of activated components. The final decontamination and decommissioning (D and D) would then be performed using then-current methodology in a safe and efficient manner. the philosophy has now changed to close coupling the initial deactivation with final D and D. This paper presents the status of the facility and focuses on the future challenge of sodium removal.

FARABEE, O.A.

2006-02-24T23:59:59.000Z

388

Second Line of Defense Megaports Initiative Operational Testing and Evaluation Plan Colon Container Terminal (CCT) Panama  

SciTech Connect (OSTI)

Report on the Operational Testing and Evaluation to validate and baseline an operable system that meets the Second Line of Defense (SLD) mission requirements. An SLD system is defined as the detection technology and associated equipment, the system operators from the host country, the standard operating procedures (SOPs), and other elements such as training and maintenance which support long-term system sustainment. To this end, the activities conducted during the OT&E phase must demonstrate that the Megaports System can be operated effectively in real-time by Panama Direccion General de Aduanas (DGA Panama Customs) personnel to the standards of the U.S. Department of Energy/National Nuclear Security Administration (DOE/NNSA).

Newhouse, Robert N.

2010-01-01T23:59:59.000Z

389

Long-term Monitoring Plan for the Central Nevada Test Area  

SciTech Connect (OSTI)

The groundwater flow and transport model of the Faultless underground nuclear test conducted at the Central Nevada Test Area (CNTA) was accepted by the state regulator and the environmental remediation efforts at the site have progressed to the stages of model validation and long-term monitoring design. This report discusses the long-term monitoring strategy developed for CNTA. Subsurface monitoring is an expensive and time-consuming process, and the design approach should be based on a solid foundation. As such, a thorough literature review of monitoring network design is first presented. Monitoring well networks can be designed for a number of objectives including aquifer characterization, parameter estimation, compliance monitoring, detection monitoring, ambient monitoring, and research monitoring, to name a few. Design methodologies also range from simple hydrogeologic intuition-based tools to sophisticated statistical- and optimization-based tools. When designing the long-term monitoring well network for CNTA, a number of issues are carefully considered. These are the uncertainty associated with the subsurface environment and its implication for monitoring design, the cost associated with monitoring well installation and operation, the design criteria that should be used to select well locations, and the potential conflict between different objectives such as early detection versus impracticality of placing wells in the vicinity of the test cavity. Given these considerations and the literature review of monitoring design studies, a multi-staged approach for development of the long-term monitoring well network for CNTA is proposed. This multi-staged approach will proceed in parallel with the validation efforts for the groundwater flow and transport model of CNTA. Two main stages are identified as necessary for the development of the final long-term monitoring well network for the site. The first stage is to use hydrogeologic expertise combined with model simulations and probability based approaches to select the first set of monitoring wells that will serve two purposes. The first is to place the wells in areas likely to encounter migration pathways thereby enhancing the probability of detecting radionuclide migration in the long run. The second objective is crucial in the short run and is aimed at using this set of wells to collect validation data for the model. The selection criteria should thus balance these two objectives. Based on the results of the validation process that progresses concurrently with the first monitoring stage, either more wells will be needed in this first stage or the second stage will be initiated. The second monitoring design stage will be based on an optimum design methodology that uses a suitable statistical approach, combined with an optimization approach, to augment the initial set of wells and develop the final long-term monitoring network. The first-stage probabilistic analysis conducted using the CNTA model indicates that the likelihood of migration away from the test cavity is very low and the probability of detecting radionuclides in the next 100 years is extremely low. Therefore, it is recommended to place one well in the downstream direction along the model longitudinal centerline (i.e., directly north of the working point), which is the location with the highest probability of encountering the plume. Lack of significant plume spreading, coupled with the extremely low velocities, suggests that this one well is sufficient for the first stage. Data from this well, and from additional wells located with validation as the prime objective, will benefit the model validation process. In the long run, this first monitoring well is going to be crucial for the long-term monitoring of the site (assuming that the flow model is validated), as it will be the most likely place to detect any plume migration away from the cavity.

A. Hassan

2003-09-02T23:59:59.000Z

390

Streamlined approach for environmental restoration plan for corrective action unit 430, buried depleted uranium artillery round No. 1, Tonopah test range  

SciTech Connect (OSTI)

This plan addresses actions necessary for the restoration and closure of Corrective Action Unit (CAU) No. 430, Buried Depleted Uranium (DU) Artillery Round No. 1 (Corrective Action Site No. TA-55-003-0960), a buried and unexploded W-79 Joint Test Assembly (JTA) artillery test projectile with high explosives (HE), at the U.S. Department of Energy, Nevada Operations Office (DOE/NV) Tonopah Test Range (TTR) in south-central Nevada. It describes activities that will occur at the site as well as the steps that will be taken to gather adequate data to obtain a notice of completion from Nevada Division of Environmental Protection (NDEP). This plan was prepared under the Streamlined Approach for Environmental Restoration (SAFER) concept, and it will be implemented in accordance with the Federal Facility Agreement and Consent Order (FFACO) and the Resource Conservation and Recovery Act (RCRA) Industrial Sites Quality Assurance Project Plan.

NONE

1996-09-01T23:59:59.000Z

391

Existing and Past Methods of Test and Rating Standards Related to Integrated Heat Pump Technologies  

SciTech Connect (OSTI)

This report evaluates existing and past US methods of test and rating standards related to electrically operated air, water, and ground source air conditioners and heat pumps, 65,000 Btu/hr and under in capacity, that potentiality incorporate a potable water heating function. Two AHRI (formerly ARI) standards and three DOE waivers were identified as directly related. Six other AHRI standards related to the test and rating of base units were identified as of interest, as they would form the basis of any new comprehensive test procedure. Numerous other AHRI and ASHRAE component test standards were also identified as perhaps being of help in developing a comprehensive test procedure.

Reedy, Wayne R. [Sentech, Inc.

2010-07-01T23:59:59.000Z

392

Walkability Planning in Jakarta  

E-Print Network [OSTI]

Integrated accessibility strategy and design Legibility Integrated activity Shared spaces Strategy 1: Policy Pedestrian planning as constituency buildingIntegrated activity study Inclusive road designation WikiPlaces pedestrian network mapping Vernacular placemaking and Asian shared street design Pedestrian planning as constituency building

Lo, Ria S. Hutabarat

2011-01-01T23:59:59.000Z

393

Corrective Action Plan for Corrective Action Unit 543: Liquid Disposal Units, Nevada Test Site, Nevada  

SciTech Connect (OSTI)

Corrective Action Unit (CAU) 543, Liquid Disposal Units, is listed in Appendix III of the Federal Facility Agreement and Consent Order of 1996. CAU 543 consists of seven Corrective Action Sites (CASs) located in Areas 6 and 15 of the Nevada Test Site, which is approximately 65 miles northwest of Las Vegas, Nevada. CAU 543 consists of the following seven CASs: {sm_bullet} CAS 06-07-01, Decon Pad {sm_bullet} CAS 15-01-03, Aboveground Storage Tank {sm_bullet} CAS 15-04-01, Septic Tank {sm_bullet} CAS 15-05-01, Leachfield {sm_bullet} CAS 15-08-01, Liquid Manure Tank {sm_bullet} CAS 15-23-01, Underground Radioactive Material Area {sm_bullet} CAS 15-23-03, Contaminated Sump, Piping From January 24, 2005 through April 14, 2005, CAU 543 site characterization activities were conducted, and are reported in Appendix A of the CAU 543 Corrective Action Decision Document (CADD) (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2005). The recommended corrective action as stated in the approved CADD is No Further Action for five of the CAU 543 CASs, and Closure In Place for the remaining two CASs.

NSTec Environmental Restoration

2006-09-01T23:59:59.000Z

394

CLOSURE OF THE FAST FLUX TEST FACILITY (FFTF) CURRENT STATUS & FUTURE PLANS  

SciTech Connect (OSTI)

The Fast Flux Test Facility (FFTF) was a 400 MWt sodium-cooled fast reactor situated on the U.S. Department of Energy's (DOE) Hanford Site in the southeastern portion of Washington State. DOE issued the final order to shut down the facility in 2001, when it was concluded that there was no longer a need for FFTF. Deactivation activities are in progress to remove or stabilize major hazards and deactivate systems to achieve end points documented in the project baseline. The reactor has been defueled, and approximately 97% of the fuel has been removed from the facility. Approximately 97% of the sodium has been drained from the plant's systems and placed into an on-site Sodium Storage Facility. The residual sodium will be kept frozen under a blanket of inert gas until it is removed later as part of the facility's decontamination and decommissioning (D&D). Plant systems have been shut down and placed in a low-risk state to minimize requirements for surveillance and maintenance. D&D work cannot begin until an Environmental Impact Statement has been prepared to evaluate various end state options and to provide a basis for selecting one of the options. The Environmental Impact Statement is expected to be issued in 2009.

LESPERANCE, C.P.

2007-05-23T23:59:59.000Z

395

Progress Letter Report on Bending Fatigue Test System Development for Spent Nuclear Fuel Vibration Integrity Study (Out-of-cell fatigue testing development - Task 2.4)  

SciTech Connect (OSTI)

Vibration integrity of high burn-up spent nuclear fuel in transportation remains to be a critical component of US nuclear waste management system. The structural evaluation of package for spent fuel transportation eventually will need to see if the content or spent fuel is in a subcritical condition. However, a system for testing and characterizing such spent fuel is still lacking mainly due to the complication involved with dealing radioactive specimens in a hot cell environment. Apparently, the current state-of-the-art in spent fuel research and development is quite far away from the delivery of reliable mechanical property data for the assessment of spent fuels in the transport package evaluation. Under the sponsorship of US NRC, ORNL has taken the challenge in developing a robust testing system for spent fuel in hot cell. An extensive literature survey was carried out and unique requirements of such testing system were identified. The U-frame setup has come to the top among various designs examined for reverse bending fatigue test of spent fuel rod. The U-frame has many features that deserve mentioned here: Easy to install spent fuel rod in test; Less linkages than in conventional bending test setup such as three-point or four-point bending; Target the failure mode relevant to the fracture of spent fuel rod in transportation by focusing on pure bending; The continuous calibrations and modifications resulted in the third generation (3G) U-frame testing setup. Rigid arms are split along the LBB axis at rod sample ends. For each arm, this results in a large arm body and an end piece. Mating halves of bushings were modified into two V-shaped surfaces on which linear roller bearings (LRB) are embedded. The rod specimen is installed into the test fixture through opening and closing slide end-pieces. The 3G apparently has addressed major issues of setup identified in the previous stage and been proven to be eligible to be further pursued in this project. On the other hand, the purchase of universal testing machine or Bose dual LM2 TB was completed and the testing system was delivered to ORNL in August 2012. The preliminary confirmation of the system and on-site training were given by Bose field engineer and regional manager on 8/1-8/2/2012. The calibration of Bose testing system has been performed by ORNL because the integration of ORNL setup into the Bose TestBench occurred after the installation. Major challenge with this process arose from two aspects: 1) the load control involves two load cells, and 2) U-frame setup itself is a non-standard specimen. ORNL has been able to implement the load control through Cycle Indirect along with pinning the U-frame setup. Two meetings with ORNL hot-cell group (November 2012 and January 2013) were held to discuss the potential issues with both epoxy mounting of rigid sleeve and U-frame setup. Many suggestions were provided to make the procedure friendlier to the manipulator in hot cell. Addressing of these suggestions resulted in another cycle of modifications of both vise mold and setup. The initial meeting with ORNL I&C group occurred in November 2012 with regard to the Bose cable modification and design of central panel to integrate the cables and wires. The first round of cable modification and central panel fabrication was completed in February 2012. The testing with the modified cables exhibited substantial noises and the testing system was not shown to be stable. It was believed the cross talk was responsible to the noise, and a central panel with a better grounding and shielding was highly recommended. The central panel has been re-designed and fabricated in March 2013. In the subsequent period, the ORNL made substantial effort to debug the noises with the load cell channel, and to resolve the noises and nonlinearity with RDP LVDTs related to the integration of RDP LVDTs to Bose system. At the same time, ORNL has completed the verification tests of Bose test system, including cycle tests under reversal bending in load control, bending tests under monotonic load, and cycle test

Wang, Jy-An John [ORNL; Wang, Hong [ORNL; Cox, Thomas S [ORNL; Baldwin, Charles A [ORNL; Bevard, Bruce Balkcom [ORNL

2013-08-01T23:59:59.000Z

396

Plan for Using Solar-Powered Jack Pumps to Sample Groundwater at the Nevada Test Site  

SciTech Connect (OSTI)

Groundwater is sampled from 39 monitoring wells on the Nevada Test Site (NTS) as part of the Routine Radiological Environmental Monitoring Program. Many of these wells were not designed or constructed for long-term groundwater monitoring. Some have extensive completion zones and others have obstructions such as pumps and tubing. The high-volume submersible pumps in some wells are unsuitable for long-term monitoring and result in large volumes of water that may have to be contained and characterized before subsequent disposition. The configuration of most wells requires sampling stagnant well water with a wireline bailer. Although bailer sampling allows for the collection of depth-discrete samples, the collected samples may not be representative of local groundwater because no well purging is done. Low-maintenance, solar-powered jack pumps will be deployed in nine of these onsite monitoring wells to improve sample quality. These pumps provide the lift capacity to produce groundwater from the deep aquifers encountered in the arid environment of the NTS. The water depths in these wells range from 700 to 2,340 ft below ground surface. The considerable labor and electrical power requirements of electric submersible pumps are eliminated once these pumps are installed. Access tubing will be installed concurrent with the installation of the pump string to provide downhole access for water-level measurements or other wireline instruments. Micro-purge techniques with low pump rates will be used to minimize purge volumes and reduce hydraulic gradients. The set depths of the pumps will be determined by the borehole characteristics and screened interval.

David Hudson, Charles Lohrstorfer, Bruce Hurley

2007-05-03T23:59:59.000Z

397

PEP Integrated Test D Run Report Caustic and Oxidative Leaching in UFP-VSL-T02A  

SciTech Connect (OSTI)

Pacific Northwest National Laboratory (PNNL) has been tasked by Bechtel National Inc. (BNI) on the River Protection Project-Hanford Tank Waste Treatment and Immobilization Plant (RPP-WTP) project to perform research and development activities to resolve technical issues identified for the Pretreatment Facility (PTF). The Pretreatment Engineering Platform (PEP) was designed, constructed and operated as part of a plan to respond to issue M12, "Undemonstrated Leaching Processes" of the External Flowsheet Review Team (EFRT) issue response plan. The PEP is a 1/4.5-scale test platform designed to simulate the WTP pretreatment caustic leaching, oxidative leaching, ultrafiltration solids concentration, and slurry washing processes. The PEP replicates the WTP leaching processes using prototypic equipment and control strategies. The PEP also includes non-prototypic ancillary equipment to support the core processing. Two operating scenarios are currently being evaluated for the ultrafiltration process (UFP) and leaching operations. The first scenario (Test B and D) has caustic leaching performed in the UFP-2 ultrafiltration feed vessels (i.e., vessel UFP-VSL-T02A in the PEP and vessels UFP-VSL-00002A and B in the WTP PTF). The second scenario (Test A) has caustic leaching conducted in the UFP-1 ultrafiltration feed preparation vessels (i.e., vessels UFP-VSL-T01A and B in the PEP and vessels UFP VSL-00001A and B in the WTP PTF). In Test D, 19M sodium hydroxide (NaOH, caustic) was added to the waste slurry in the UFP VSL T02 vessel after the solids were concentrated to ~20% undissolved solids. The NaOH was added to leach solid aluminum compounds (e.g., gibbsite, boehmite). Caustic addition is followed by heating to 85°C using direct injection of steam to accelerate the leach process. The main difference of Test D compared to Test B is that the leach temperature is 85°C for 24 hrs as compared to 100°C for 12 hours. The other difference is the Test D simulant had Cr in the simulant from the start of processing and Test B had Cr added to adjust the simulant composition after aluminum leaching. Following the caustic leach, the UFP-VSL-T02A vessel contents are cooled using the vessel cooling jacket. The slurry was then concentrated to 17 wt% undissolved solids and washed with inhibited water to remove NaOH and other soluble salts. Next, the slurry was oxidatively leached using sodium permanganate to solubilize chrome. The slurry was then washed to remove the dissolved chrome and concentrated.

Sevigny, Gary J.; Bredt, Ofelia P.; Burns, Carolyn A.; Kurath, Dean E.; Geeting, John GH; Golovich, Elizabeth C.; Guzman-Leong, Consuelo E.; Josephson, Gary B.

2009-12-11T23:59:59.000Z

398

Corrective Action Investigation Plan for Corrective Action Unit 562: Waste Systems Nevada Test Site, Nevada, Revision 0  

SciTech Connect (OSTI)

Corrective Action Unit 562 is located in Areas 2, 23, and 25 of the Nevada Test Site, which is approximately 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 562 is comprised of the 13 corrective action sites (CASs) listed below: • 02-26-11, Lead Shot • 02-44-02, Paint Spills and French Drain • 02-59-01, Septic System • 02-60-01, Concrete Drain • 02-60-02, French Drain • 02-60-03, Steam Cleaning Drain • 02-60-04, French Drain • 02-60-05, French Drain • 02-60-06, French Drain • 02-60-07, French Drain • 23-60-01, Mud Trap Drain and Outfall • 23-99-06, Grease Trap • 25-60-04, Building 3123 Outfalls These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Additional information will be obtained by conducting a corrective action investigation before evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on December 11, 2008, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and National Security Technologies, LLC. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 562. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the corrective action investigation for CAU 562 includes the following activities: • Move surface debris and/or materials, as needed, to facilitate sampling. • Conduct radiological surveys. • Perform field screening. • Collect and submit environmental samples for laboratory analysis to determine the nature and extent of any contamination released by each CAS. • Collect samples of source material to determine the potential for a release. • Collect samples of potential remediation wastes. • Collect quality control samples. This Corrective Action Investigation Plan has been developed in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; DOE, Environmental Management; U.S. Department of Defense; and DOE, Legacy Management (FFACO, 1996; as amended February 2008). Under the Federal Facility Agreement and Consent Order, this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Fieldwork will be conducted following approval of the plan.

Alfred Wickline

2009-04-01T23:59:59.000Z

399

Integrated Dry NO sub x /SO sub 2 Emissions Control System baseline test report, November 11--December 15, 1991  

SciTech Connect (OSTI)

The DOE sponsored Integrated Dry NO{sub x}/SO{sub 2} Emissions Control System program, which is a Clean Coal Technology Ill demonstration, is being conducted by Public Service Company of Colorado. The test site is Arapahoe Generating Station Unit 4, which is a 100 MWe, down-fired utility boiler burning a low sulfur western coal. The project goal is to demonstrate 70 percent reductions in NO{sub x} and S0{sub 2} emissions through the integration of: (1) down-fired low-NO{sub x} burners with overfire air; (2) urea injection for additional NO{sub x} removal; and (3) dry sorbent injection and duct humidification for SO{sub 2} removal. The effectiveness of the integrated system on a high sulfur coal will also be tested. This report documents the first baseline test results conducted during the program. The baseline tests were conducted with the original burners and auxiliary equipment and represent the unmodified boiler emissions. The burner design of Arapahoe Unit 4 results in relatively high NO{sub x} levels ranging from 740 to 850 ppM (corrected to 3% O{sub 2}, dry) over the load range. Excess air level was the primary factor influencing NO{sub x} emissions. During normal boiler operations, there was a wide range in NO{sub x} emissions, due to the variations of excess air, boiler load and other, secondary parameters. SO{sub 2} emissions ranged from 350 to 600 ppM (corrected to 3% O{sub 2}, dry) and reflected variations in the coal sulfur content.

Shiomoto, G.H.; Smith, R.A.

1992-03-01T23:59:59.000Z

400

A wideband frequency synthesizer for built-in self testing of analog integrated circuits  

E-Print Network [OSTI]

leading to the use of built-in self-tests (BISTs). The frequency generator or frequency synthesizer is a key element of the BIST. It generates the clock frequencies needed for testing. A wide-band frequency synthesizer is designed in the project...

Yan, Wenjian

2004-11-15T23:59:59.000Z

Note: This page contains sample records for the topic "integrated test plan" 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

Couplingbased Criteria for Integration Testing \\Lambda Zhenyi Jin and A. Jefferson Offutt  

E-Print Network [OSTI]

, Software testing. 1 Introduction Testing software is one of the most common methods for assuring quality quality and reliability. Such criteria also provide stopping rules and repeatability. A program unit that the tester will find any faults in the program and providing greater assurance that the software is of high

Offutt, Jeff

402

Corrective Action Decision Document/Corrective Action Plan for Corrective Action Unit 104: Area 7 Yucca Flat Atmospheric Test Sites Nevada National Security Site, Nevada, Revision 0  

SciTech Connect (OSTI)

CAU 104 comprises the following corrective action sites (CASs): • 07-23-03, Atmospheric Test Site T-7C • 07-23-04, Atmospheric Test Site T7-1 • 07-23-05, Atmospheric Test Site • 07-23-06, Atmospheric Test Site T7-5a • 07-23-07, Atmospheric Test Site - Dog (T-S) • 07-23-08, Atmospheric Test Site - Baker (T-S) • 07-23-09, Atmospheric Test Site - Charlie (T-S) • 07-23-10, Atmospheric Test Site - Dixie • 07-23-11, Atmospheric Test Site - Dixie • 07-23-12, Atmospheric Test Site - Charlie (Bus) • 07-23-13, Atmospheric Test Site - Baker (Buster) • 07-23-14, Atmospheric Test Site - Ruth • 07-23-15, Atmospheric Test Site T7-4 • 07-23-16, Atmospheric Test Site B7-b • 07-23-17, Atmospheric Test Site - Climax These 15 CASs include releases from 30 atmospheric tests conducted in the approximately 1 square mile of CAU 104. Because releases associated with the CASs included in this CAU overlap and are not separate and distinguishable, these CASs are addressed jointly at the CAU level. The purpose of this CADD/CAP is to evaluate potential corrective action alternatives (CAAs), provide the rationale for the selection of recommended CAAs, and provide the plan for implementation of the recommended CAA for CAU 104. Corrective action investigation (CAI) activities were performed from October 4, 2011, through May 3, 2012, as set forth in the CAU 104 Corrective Action Investigation Plan.

Patrick Matthews

2012-10-01T23:59:59.000Z

403

INTEGRAL BENCHMARK DATA FOR NUCLEAR DATA TESTING THROUGH THE ICSBEP AND THE NEWLY ORGANIZED IRPHEP  

SciTech Connect (OSTI)

The status of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) was last reported in a nuclear data conference at the International Conference on Nuclear Data for Science and Technology, ND-2004, in Santa Fe, New Mexico. Since that time the number and type of integral benchmarks have increased significantly. Included in the ICSBEP Handbook are criticality-alarm / shielding and fundamental physic benchmarks in addition to the traditional critical / subcritical benchmark data. Since ND 2004, a reactor physics counterpart to the ICSBEP, the International Reactor Physics Experiment Evaluation Project (IRPhEP) was initiated. The IRPhEP is patterned after the ICSBEP, but focuses on other integral measurements, such as buckling, spectral characteristics, reactivity effects, reactivity coefficients, kinetics measurements, reaction-rate and power distributions, nuclide compositions, and other miscellaneous-type measurements in addition to the critical configuration. The status of these two projects is discussed and selected benchmarks highlighted in this paper.

J. Blair Briggs; Lori Scott; Yolanda Rugama; Enrico Satori

2007-04-01T23:59:59.000Z

404

Corrective Action Investigation Plan for Corrective Action Unit 98: Frenchman Flat, Nevada Test Site, Nevada (Revision 1)  

SciTech Connect (OSTI)

This Corrective Action Investigation Plan (CAIP) has been developed for Frenchman Flat Corrective Action Unit (CAU) 98. The Frenchman Flat CAU is located along the eastern border of the Nevada Test Site (NTS) and includes portions of Areas 5 and 11. The Frenchman Flat CAU constitutes one of several areas of the Nevada Test Site used for underground nuclear testing in the past. The nuclear tests resulted in groundwater contamination in the vicinity as well as downgradient of the underground test areas. The CAIP describes the Corrective Action Investigation (CAI) to be conducted at the Frenchman Flat CAU to evaluate the extent of contamination in groundwater due to the underground nuclear testing. The Frenchman Flat CAI will be conducted by the Underground Test Area (UGTA) Project which is a part of the U.S. Department of Energy, Nevada Operations Office (DOE/NV) Environmental Restoration Project. The CAIP is a requirement of the Federal Facility Agreement and Consent Order (FFACO) (1996 ) agreed to by the U.S. Department of Energy (DOE), the Nevada Division of Environmental Protection (NDEP), and the U.S. Department of Defense (DoD). Based on the general definition of a CAI from Section IV.14 of the FFACO, the purpose of the CAI is ''...to gather data sufficient to characterize the nature, extent, and rate of migration or potential rate of migration from releases or discharges of pollutants or contaminants and/or potential releases or discharges from corrective action units identified at the facilities...'' (FFACO, 1996). However, for the Underground Test Area (UGTA) CAUs, ''...the objective of the CAI process is to define boundaries around each UGTA CAU that establish areas that contain water that may be unsafe for domestic and municipal use.'', as stated in Appendix VI of the FFACO (1996). According to the UGTA strategy (Appendix VI of the FFACO), the CAI of a given CAU starts with the evaluation of the existing data. New data collection activities are generally contingent upon the results of the modeling and may or may not be part of the CAI. Such is the case for the Frenchman Flat CAU. The current scope of the Frenchman Flat CAI includes the development and use of a three-dimensional (3-D), numerical, CAU-scale groundwater flow and contaminant transport model to predict the location of the contaminant boundary. The CAU model will be developed and used to predict the location of the contaminant boundary. The scope of this CAI does not currently include any characterization activities; however, such activities will be conducted if the CAU model results indicate that further characterization information is needed to develop a sufficiently reliable CAU model. Two areas of importance to the CAU model are the model area and the investigation area. The CAU-model area will be selected to encompass the Frenchman Flat CAU and the region located immediately downgradient where contamination may migrate. The extent of the CAU-model area is dependent on the extent of contamination and is uncertain at this point. The extent of the investigation area is not expected to increase during the CAI.

USDOE/NV

1999-07-01T23:59:59.000Z

405

The TST: A small Steady-State Tokamak for Integrated Divertor Testing  

SciTech Connect (OSTI)

This report discusses the following topics: The TST program; the TST physics basis; the TST auxiliary H&CD systems; the test divertors; the TST device; and ancillary systems.

Peng, Y.K.M.; Colchin, R.J.; Swain, D.W.; Nelson, B.E.; Monday, J.F.

1993-09-01T23:59:59.000Z

406

Corrective Action Investigation Plan for Corrective Action Unit 554: Area 23 Release Site, Nevada Test Site, Nevada, Rev. No.: 0  

SciTech Connect (OSTI)

This Corrective Action Investigation Plan (CAIP) contains project-specific information for conducting site investigation activities at Corrective Action Unit (CAU) 554: Area 23 Release Site, Nevada Test Site, Nevada. Information presented in this CAIP includes facility descriptions, environmental sample collection objectives, and criteria for the selection and evaluation of environmental samples. Corrective Action Unit 554 is located in Area 23 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 554 is comprised of one Corrective Action Site (CAS), which is: 23-02-08, USTs 23-115-1, 2, 3/Spill 530-90-002. This site consists of soil contamination resulting from a fuel release from underground storage tanks (USTs). Corrective Action Site 23-02-08 is being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Additional information will be obtained by conducting a corrective action investigation prior to evaluating corrective action alternatives and selecting the appropriate corrective action for this CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document for CAU 554. Corrective Action Site 23-02-08 will be investigated based on the data quality objectives (DQOs) developed on July 15, 2004, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; and contractor personnel. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 554.

David A. Strand

2004-10-01T23:59:59.000Z

407

Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC) verification and validation plan. version 1.  

SciTech Connect (OSTI)

The objective of the U.S. Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC) is to provide an integrated suite of computational modeling and simulation (M&S) capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive-waste storage facility or disposal repository. To meet this objective, NEAMS Waste IPSC M&S capabilities will be applied to challenging spatial domains, temporal domains, multiphysics couplings, and multiscale couplings. A strategic verification and validation (V&V) goal is to establish evidence-based metrics for the level of confidence in M&S codes and capabilities. Because it is economically impractical to apply the maximum V&V rigor to each and every M&S capability, M&S capabilities will be ranked for their impact on the performance assessments of various components of the repository systems. Those M&S capabilities with greater impact will require a greater level of confidence and a correspondingly greater investment in V&V. This report includes five major components: (1) a background summary of the NEAMS Waste IPSC to emphasize M&S challenges; (2) the conceptual foundation for verification, validation, and confidence assessment of NEAMS Waste IPSC M&S capabilities; (3) specifications for the planned verification, validation, and confidence-assessment practices; (4) specifications for the planned evidence information management system; and (5) a path forward for the incremental implementation of this V&V plan.

Bartlett, Roscoe Ainsworth; Arguello, Jose Guadalupe, Jr.; Urbina, Angel; Bouchard, Julie F.; Edwards, Harold Carter; Freeze, Geoffrey A.; Knupp, Patrick Michael; Wang, Yifeng; Schultz, Peter Andrew; Howard, Robert (Oak Ridge National Laboratory, Oak Ridge, TN); McCornack, Marjorie Turner

2011-01-01T23:59:59.000Z

408

2014-06-18 Issuance: Test Procedure for Integrated Light-Emitting Diode Lamps; Supplemental Notice of Proposed Rulemaking  

Broader source: Energy.gov [DOE]

This document is a pre-publication Federal Register Supplemental Notice of Proposed Rulemaking regarding Test Procedures for Integrated Light-Emitting Diode Lamps, as issued by the Deputy Assistant Secretary for Energy Efficiency on June 18, 2014. Though it is not intended or expected, should any discrepancy occur between the document posted here and the document published in the Federal Register, the Federal Register publication controls. This document is being made available through the Internet solely as a means to facilitate the public's access to this document.

409

Corrective Action Plan for Corrective Action Unit 166: Storage Yards and Contaminated Materials, Nevada Test Site, Nevada  

SciTech Connect (OSTI)

Corrective Action Unit (CAU) 166, Storage Yards and Contaminated Materials, is listed in the Federal Facility Agreement and Consent Order (FFACO) of 1996 (FFACO, 1996). CAU 166 consists of seven Corrective Action Sites (CASs) located in Areas 2, 3, 5, and 18 of the Nevada Test Site (NTS), which is located approximately 65 miles northwest of Las Vegas, Nevada (Figure 1). CAU 166 consists of the following CASs: (1) CAS 02-42-01, Cond. Release Storage Yd - North; (2) CAS 02-42-02, Cond. Release Storage Yd - South; (3) CAS 02-99-10, D-38 Storage Area; (4) CAS 03-42-01, Conditional Release Storage Yard; (5) CAS 05-19-02, Contaminated Soil and Drum; (6) CAS 18-01-01, Aboveground Storage Tank; and (7) CAS 18-99-03, Wax Piles/Oil Stain. Details of the site history and site characterization results for CAU 166 are provided in the approved Corrective Action Investigation Plan (CAIP) (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2006) and in the approved Corrective Action Decision Document (CADD) (NNSA/NSO, 2007).

NSTec Environmental Restoration

2007-10-01T23:59:59.000Z

410

Corrective Action Plan for Corrective Action Unit 143: Area 25 Contaminated Waste Dumps, Nevada Test Site, Nevada  

SciTech Connect (OSTI)

This Corrective Action Plan (CAP) has been prepared for Corrective Action Unit (CAU) 143: Area 25 Contaminated Waste Dumps, Nevada Test Site, Nevada, in accordance with the Federal Facility Agreement and Consent Order of 1996. This CAP provides the methodology for implementing the approved corrective action alternative as listed in the Corrective Action Decision Document (U.S. Department of Energy, Nevada Operations Office, 2000). The CAU includes two Corrective Action Sites (CASs): 25-23-09, Contaminated Waste Dump Number 1; and 25-23-03, Contaminated Waste Dump Number 2. Investigation of CAU 143 was conducted in 1999. Analytes detected during the corrective action investigation were evaluated against preliminary action levels to determine constituents of concern for CAU 143. Radionuclide concentrations in disposal pit soil samples associated with the Reactor Maintenance, Assembly, and Disassembly Facility West Trenches, the Reactor Maintenance, Assembly, and Disassembly Facility East Trestle Pit, and the Engine Maintenance, Assembly, and Disassembly Facility Trench are greater than normal background concentrations. These constituents are identified as constituents of concern for their respective CASs. Closure-in-place with administrative controls involves use restrictions to minimize access and prevent unauthorized intrusive activities, earthwork to fill depressions to original grade, placing additional clean cover material over the previously filled portion of some of the trenches, and placing secondary or diversion berm around pertinent areas to divert storm water run-on potential.

D. L. Gustafason

2001-02-01T23:59:59.000Z

411

Corrective Action Investigation Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks Nevada Test Site, Nevada  

SciTech Connect (OSTI)

This Corrective Action Investigation Plan (CAIP) has been developed in accordance with the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the US Department of Energy, Nevada Operations Office (DOE/NV); the State of Nevada Division of Environmental Protection (NDEP); and the US Department of Defense (FFACO, 1996). The CAIP is a document that provides or references all of the specific information for investigation activities associated with Corrective Action Units (CAUs) or Corrective Action Sites (CASs). According to the FFACO, CASs are sites potentially requiring corrective action(s) and may include solid waste management units or individual disposal or release sites (FFACO, 1996). Corrective Action Units consist of one or more CASs grouped together based on geography, technical similarity, or agency responsibility for the purpose of determining corrective actions. This CAIP contains the environmental sample collection objectives and the criteria for conducting site investigation activities at CAU 135, Area 25 Underground Storage Tanks (USTs), which is located on the Nevada Test Site (NTS). The NTS is approximately 105 kilometers (km) (65 miles [mi]) northwest of Las Vegas, Nevada.

U.S. Department of Energy, Nevada Operations Office

1999-05-05T23:59:59.000Z

412

Corrective Action Investigation Plan for Corrective Action Unit 240: Area 25 Vehicle Washdown Nevada Test Site, Nevada  

SciTech Connect (OSTI)

This Corrective Action Investigation Plan (CAIP) has been developed in accordance with the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the US Department of Energy, Nevada Operations Office (DOE/NV); the State of Nevada Division of Environmental Protection (NDEP); and the US Department of Defense (FFACO, 1996). The CAIP is a document that provides or references all of the specific information for investigation activities associated with Corrective Action Units (CAUs) or Corrective Action Sites (CASs). According to the FFACO, CASs are sites potentially requiring corrective action(s) and may include solid waste management units or individual disposal or release sites (FFACO, 1996). Corrective Action Units consist of one or more CASs grouped together based on geography, technical similarity, or agency responsibility for the purpose of determining corrective actions. This CAIP contains the environmental sample collection objectives and the criteria for conducting site investigation activities at CAU 240, Area 25 Vehicle Washdown, which is located on the Nevada Test Site (NTS).

DOE/NV

1999-01-25T23:59:59.000Z

413

TEST PLAN AND PROCEDURE FOR THE EXAMINATION OF TANK 241-AY-101 MULTI-PROBE CORROSION MONITORING SYSTEM  

SciTech Connect (OSTI)

This test plan describes the methods to be used in the forensic examination of the Multi-probe Corrosion Monitoring System (MPCMS) installed in the double-shell tank 241-AY-101 (AY-101). The probe was designed by Applied Research and Engineering Sciences (ARES) Corporation. The probe contains four sections, each of which can be removed from the tank independently (H-14-107634, AY-101 MPCMS Removable Probe Assembly) and one fixed center assembly. Each removable section contains three types of passive corrosion coupons: bar coupons, round coupons, and stressed C-rings (H-14-l07635, AY-101 MPCMS Details). Photographs and weights of each coupon were recorded and reported on drawing H-14-107634 and in RPP-RPT-40629, 241-AY-101 MPCMS C-Ring Coupon Photographs. The coupons will be the subject of the forensic analyses. The purpose of this examination will be to document the nature and extent of corrosion of the 29 coupons. This documentation will consist of photographs and photomicrographs of the C-rings and round coupons, as well as the weights of the bar and round coupons during corrosion removal. The total weight loss of the cleaned coupons will be used in conjunction with the surface area of each to calculate corrosion rates in mils per year. The bar coupons were presumably placed to investigate the liquid-air-interface. An analysis of the waste level heights in the waste tank will be investigated as part of this examination.

WYRWAS RB; PAGE JS; COOKE GS

2012-04-19T23:59:59.000Z

414

Corrective Action Investigation Plan for Corrective Action Unit 552: Area 12 Muckpile and Ponds, Nevada Test Site, Nevada: Revision 0  

SciTech Connect (OSTI)

This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's approach for collecting the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 552: Area 12 Muckpile and Ponds, Nevada Test Site (NTS), Nevada, under the Federal Facility Agreement and Consent Order. Located in Area 12 on the NTS, CAU 552 consists of two Corrective Action Sites (CASs): 12-06-04, Muckpile; 12-23-05, Ponds. Corrective Action Site 12-06-04 in Area 12 consists of the G-Tunnel muckpile, which is the result of tunneling activities. Corrective Action Site 12-23-05 consists of three dry ponds adjacent to the muckpile. The toe of the muckpile extends into one of the ponds creating an overlap of two CASs. The purpose of the investigation is to ensure that adequate data are collected to provide sufficient and reliable information to identify, evaluate, and select technic ally viable corrective actions. The results of the field investigation will support a defensible evaluation of corrective action alternatives in the corrective action decision document.

U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

2004-04-06T23:59:59.000Z

415

Achieving New Source Performance Standards (NSPS) Emission Standards Through Integration of Low-NOx Burners with an Optimization Plan for Boiler Combustion  

SciTech Connect (OSTI)

The objective of this project was to demonstrate the use of an Integrated Combustion Optimization System to achieve NO{sub X} emission levels in the range of 0.15 to 0.22 lb/MMBtu while simultaneously enabling increased power output. The project plan consisted of the integration of low-NO{sub X} burners and advanced overfire air technology with various process measurement and control devices on the Holcomb Station Unit 1 boiler. The plan included the use of sophisticated neural networks or other artificial intelligence technologies and complex software to optimize several operating parameters, including NO{sub X} emissions, boiler efficiency, and CO emissions. The program was set up in three phases. In Phase I, the boiler was equipped with sensors that can be used to monitor furnace conditions and coal flow to permit improvements in boiler operation. In Phase II, the boiler was equipped with burner modifications designed to reduce NO{sub X} emissions and automated coal flow dampers to permit on-line fuel balancing. In Phase III, the boiler was to be equipped with an overfire air system to permit deep reductions in NO{sub X} emissions. Integration of the overfire air system with the improvements made in Phases I and II would permit optimization of boiler performance, output, and emissions. This report summarizes the overall results from Phases I and II of the project. A significant amount of data was collected from the combustion sensors, coal flow monitoring equipment, and other existing boiler instrumentation to monitor performance of the burner modifications and the coal flow balancing equipment.

Wayne Penrod

2006-12-31T23:59:59.000Z

416

Corrective Action Investigation Plan for Corrective Action Unit 565: Stored Samples, Nevada Test Site, Nevada, Rev. No.: 0  

SciTech Connect (OSTI)

Corrective Action Unit (CAU) 565 is located in Area 26 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 565 is comprised of one corrective action site (CAS) listed--CAS 26-99-04, Ground Zero Soil Samples. This site is being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend closure of CAU 565. Additional information will be obtained by conducting a corrective action investigation before evaluating closure objectives and selecting the appropriate corrective action. The results of the field investigation will support closure and waste management decisions that will be presented in the Corrective Action Decision Document/Closure Report. The site will be investigated based on the data quality objectives (DQOs) developed on June 1, 2006, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and Bechtel Nevada. The DQO process was utilized to identify and define the type, amount, and quality of data needed to develop and evaluate closure for CAU 565. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to this CAS. The scope of the corrective action investigation for CAU 565 includes the following activities: (1) Remove stored samples, shelves, and debris from the interior of Building 26-2106. (2) Perform field screening on stored samples, shelves, and debris. (3) Dispose of stored samples, shelves, and debris. (4) Collect samples of investigation-derived waste, as needed, for waste management purposes. (5) Conduct radiological surveys of Building 26-2106 in accordance with the requirements in the ''NV/YMP Radiological Control Manual'' to determine if there is residual radiological contamination that would prevent the release of the building for unrestricted use. This Corrective Action Investigation has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' that was agreed to by the State of Nevada, the U.S. Department of Energy, and the U.S. Department of Defense. Under the ''Federal Facility Agreement and Consent Order'', this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Field work will be conducted following approval of the plan.

Wickline, Alfred; McCall, Robert

2006-08-01T23:59:59.000Z

417

Coupling-based Criteria for Integration Testing Zhenyi Jin and A. Je erson O utt  

E-Print Network [OSTI]

Introduction Testing software is one of the most common methods for assuring quality of complex computer will nd any faults in the program and providing greater assurance that the software is of high quality and reliability. Such criteria also provide stopping rules and repeatability. A program unit, or procedure, is one

Offutt, Jeff

418

Integrating Long-Term Avian Studies with Planning and Adaptive Management: Department of Energy Lands as a Case Study.  

SciTech Connect (OSTI)

Long-term bio-monitoring of avian communities have been initiated, but they often lack a management component. Integration of the managers needs at an early stage is suggested as a means to increase the use of the data. Variation in community structure is important in understanding impacts. In addition, reference site must be carefully selected.

Burger, J.

2000-10-01T23:59:59.000Z

419

An Integrated Science Plan for the Lake Tahoe Basin: Conceptual Framework and Research Strategies Patricia N. Manley,  

E-Print Network [OSTI]

always accompany the best efforts of environmental and resource managers. They are inescapable principles and practices in an integrated fashion to acquire objective and verifiable information to fill knowledge gaps, thereby reducing uncertainties. Scientific principles and practices employed to generate new

Standiford, Richard B.

420

JV Task 46 - Development and Testing of a Thermally Integrated SOFC-Gasification System for Biomass Power Generation  

SciTech Connect (OSTI)

The Energy & Environmental Research Center has designed a biomass power system using a solid oxide fuel cell (SOFC) thermally integrated with a downdraft gasifier. In this system, the high-temperature effluent from the SOFC enables the operation of a substoichiometric air downdraft gasifier at an elevated temperature (1000 C). At this temperature, moisture in the biomass acts as an essential carbon-gasifying medium, reducing the equivalence ratio at which the gasifier can operate with complete carbon conversion. Calculations show gross conversion efficiencies up to 45% (higher heating value) for biomass moisture levels up to 40% (wt basis). Experimental work on a bench-scale gasifier demonstrated increased tar cracking within the gasifier and increased energy density of the resultant syngas. A series of experiments on wood chips demonstrated tar output in the range of 9.9 and 234 mg/m{sup 3}. Both button cells and a 100-watt stack was tested on syngas from the gasifier. Both achieved steady-state operation with a 22% and 15% drop in performance, respectively, relative to pure hydrogen. In addition, tar tolerance testing on button cells demonstrated an upper limit of tar tolerance of approximately 1%, well above the tar output of the gasifier. The predicted system efficiency was revised down to 33% gross and 27% net system efficiency because of the results of the gasifier and fuel cell experiments. These results demonstrate the feasibility and benefits of thermally integrating a gasifier and a high-temperature fuel cell in small distributed power systems.

Phillip Hutton; Nikhil Patel; Kyle Martin; Devinder Singh

2008-02-01T23:59:59.000Z

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


421

Experiment Operations Plan for a Loss-of-Coolant Accident Simulation in the National Research Universal Reactor Materials Tests 1 and 2  

SciTech Connect (OSTI)

A loss of Coolant Accident (LOCA) simulation program is evaluating the thermal-hydraulic and mechanical effects of LOCA conditions on pressurized water reactor test fuel bundles. This experiment operation plan for the second and third experiments of the program will provide peak fuel cladding temperatures of up to 1172K (1650{degree}F) and 1061K (1450{degree}) respectively. for a long enough time to cause test fuel cladding deformation and rupture in both. Reflood coolant delay times and the reflooding rates for the experiments were selected from thermal-hydraulic data measured in the National Research Universal (NRU) reactor facilities and test train assembly during the first experiment.

Russcher, G. E.; Wilson, C. L.; Marshall, R, K.; King, L. L.; Parchen, L. J.; Pilger, J. P.; Hesson, G. M.; Mohr, C. L.

1981-09-01T23:59:59.000Z

422

Corrective Action Investigation Plan for Corrective Action Unit 542: Disposal Holes, Nevada Test Site, Nevada, Rev. No.: 0  

SciTech Connect (OSTI)

Corrective Action Unit (CAU) 542 is located in Areas 3, 8, 9, and 20 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 542 is comprised of eight corrective action sites (CASs): (1) 03-20-07, ''UD-3a Disposal Hole''; (2) 03-20-09, ''UD-3b Disposal Hole''; (3) 03-20-10, ''UD-3c Disposal Hole''; (4) 03-20-11, ''UD-3d Disposal Hole''; (5) 06-20-03, ''UD-6 and UD-6s Disposal Holes''; (6) 08-20-01, ''U-8d PS No.1A Injection Well Surface Release''; (7) 09-20-03, ''U-9itsy30 PS No.1A Injection Well Surface Release''; and (8) 20-20-02, ''U-20av PS No.1A Injection Well Surface Release''. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Additional information will be obtained by conducting a corrective action investigation before evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on January 30, 2006, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and Bechtel Nevada. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 542. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the CAI for CAU 542 includes the following activities: (1) Move surface debris and/or materials, as needed, to facilitate sampling. (2) Conduct radiological surveys. (3) Conduct geophysical surveys to locate previously unidentified features at CASs 03-20-07, 03-20-09, 03-20-10, 03-20-11, and 06-20-03. (4) Perform field screening. (5) Collect and submit environmental samples for laboratory analysis to determine whether contaminants of concern (COCs) are present. (6) Collect quality control samples for laboratory analyses to evaluate the performance of measurement systems and controls based on the requirements of the data quality indicators. (7) If COCs are present at the surface/near surface (< 15 feet below ground surface), collect additional step-out samples to define the extent of the contamination. (8) If COCs are present in the subsurface (i.e., base of disposal hole), collect additional samples to define the vertical extent of contamination. A conservative use restriction will be used to encompass the lateral extent of subsurface contamination. (9) Stake or flag sample locations in the field, and record coordinates through global positioning systems surveying. (10) Collect samples of investigation-derived waste, as needed, for waste management and minimization purposes. This Corrective Action Investigation Plan has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' that was agreed to by the State of Nevada, the U.S. Department of Energy, and the U.S. Department of Defense. Under the ''Federal Facility Agreement and Consent Order'', this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Field work will be conducted following approval of the plan.

Laura Pastor

2006-05-01T23:59:59.000Z

423

NREL Tests Integrated Heat Pump Water Heater Performance in Different Climates (Fact Sheet)  

SciTech Connect (OSTI)

This technical highlight describes NREL tests to capture information about heat pump performance across a wide range of ambient conditions for five heat pump water heaters (HPWH). These water heaters have the potential to significantly reduce water heater energy use relative to traditional electric resistance water heaters. These tests have provided detailed performance data for these appliances, which have been used to evaluate the cost of saved energy as a function of climate. The performance of HPWHs is dependent on ambient air temperature and humidity and the logic controlling the heat pump and the backup resistance heaters. The laboratory tests were designed to measure each unit's performance across a range of air conditions and determine the specific logic controlling the two heat sources, which has a large effect on the comfort of the users and the energy efficiency of the system. Unlike other types of water heaters, HPWHs are both influenced by and have an effect on their surroundings. Since these effects are complex and different for virtually every house and climate region, creating an accurate HPWH model from the data gathered during the laboratory tests was a main goal of the project. Using the results from NREL's laboratory tests, such as the Coefficient of Performance (COP) curves for different air conditions as shown in Figure 1, an existing HPWH model is being modified to produce more accurate whole-house simulations. This will allow the interactions between the HPWH and the home's heating and cooling system to be evaluated in detail, for any climate region. Once these modeling capabilities are in place, a realistic cost-benefit analysis can be performed for a HPWH installation anywhere in the country. An accurate HPWH model will help to quantify the savings associated with installing a HPWH in the place of a standard electric water heater. In most locations, HPWHs are not yet a cost-effective alternative to natural gas water heaters. The detailed system performance maps that were developed by this testing program will be used to: (1) Target regions of the country that would benefit most from this technology; (2) Identify improvements in current systems to maximize homeowner cost savings; and (3) Explore opportunities for development of advanced hot water heating systems.

Not Available

2012-01-01T23:59:59.000Z

424

Method for testing the strength and structural integrity of nuclear fuel particles  

DOE Patents [OSTI]

An accurate method for testing the strength of nuclear fuel particles. Each particle includes an upper and lower portion, and is placed within a testing apparatus having upper and lower compression members. The upper compression member includes a depression therein which is circular and sized to receive only part of the upper portion of the particle. The lower compression member also includes a similar depression. The compression members are parallel to each other with the depressions therein being axially aligned. The fuel particle is then placed between the compression members and engaged within the depressions. The particle is then compressed between the compression members until it fractures. The amount of force needed to fracture the particle is thereafter recorded. This technique allows a broader distribution of forces and provides more accurate results compared with systems which distribute forces at singular points on the particle.

Lessing, Paul A. (Idaho Falls, ID)

1995-01-01T23:59:59.000Z

425

Method for testing the strength and structural integrity of nuclear fuel particles  

DOE Patents [OSTI]

An accurate method for testing the strength of nuclear fuel particles is disclosed. Each particle includes an upper and lower portion, and is placed within a testing apparatus having upper and lower compression members. The upper compression member includes a depression therein which is circular and sized to receive only part of the upper portion of the particle. The lower compression member also includes a similar depression. The compression members are parallel to each other with the depressions therein being axially aligned. The fuel particle is then placed between the compression members and engaged within the depressions. The particle is then compressed between the compression members until it fractures. The amount of force needed to fracture the particle is thereafter recorded. This technique allows a broader distribution of forces and provides more accurate results compared with systems which distribute forces at singular points on the particle. 13 figs.

Lessing, P.A.

1995-10-17T23:59:59.000Z

426

Wind-To-Hydrogen Project: Operational Experience, Performance Testing, and Systems Integration  

SciTech Connect (OSTI)

The Wind2H2 system is fully functional and continues to gather performance data. In this report, specifications of the Wind2H2 equipment (electrolyzers, compressor, hydrogen storage tanks, and the hydrogen fueled generator) are summarized. System operational experience and lessons learned are discussed. Valuable operational experience is shared through running, testing, daily operations, and troubleshooting the Wind2H2 system and equipment errors are being logged to help evaluate the reliability of the system.

Harrison, K. W.; Martin, G. D.; Ramsden, T. G.; Kramer, W. E.; Novachek, F. J.

2009-03-01T23:59:59.000Z

427

Novel scanning electron microscope bulge test technique integrated with loading function  

SciTech Connect (OSTI)

Membranes and film-on-substrate structures are critical elements for some devices in electronics industry and for Micro Electro Mechanical Systems devices. These structures are normally at the scale of micrometer or even nanometer. Thus, the measurement for the mechanical property of these membranes poses a challenge over the conventional measurements at macro-scales. In this study, a novel bulge test method is presented for the evaluation of mechanical property of micro thin membranes. Three aspects are discussed in the study: (a) A novel bulge test with a Scanning Electron Microscope system realizing the function of loading and measuring simultaneously; (b) a simplified Digital Image Correlation method for a height measurement; and (c) an imaging distortion correction by the introduction of a scanning Moiré method. Combined with the above techniques, biaxial modulus as well as Young's modulus of the polyimide film can be determined. Besides, a standard tensile test is conducted as an auxiliary experiment to validate the feasibility of the proposed method.

Li, Chuanwei; Xie, Huimin, E-mail: liuzw@bit.edu.cn, E-mail: xiehm@mail.tsinghua.edu.cn [AML, Department of Engineering Mechanics, Tsinghua University, Beijing 100084 (China); Liu, Zhanwei, E-mail: liuzw@bit.edu.cn, E-mail: xiehm@mail.tsinghua.edu.cn [School of Aerospace Engineering, Beijing Institute of Technology, Beijing 100081 (China)

2014-10-15T23:59:59.000Z

428

Corrective Action Investigation Plan for Corrective Action Unit 551: Area 12 Muckpiles, Nevada Test Site, Nevada, Rev. No.: 0  

SciTech Connect (OSTI)

This Corrective Action Investigation Plan (CAIP) contains project-specific information including facility descriptions, environmental sample collection objectives, and criteria for conducting site investigation activities at Corrective Action Unit (CAU) 551, Area 12 muckpiles, Nevada Test Site (NTS), Nevada. This CAIP has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996) that was agreed to by the State of Nevada, the U.S. Department of Energy (DOE), and the U.S. Department of Defense. Corrective Action Unit 551 is located in Area 12 of the NTS, which is approximately 110 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Area 12 is approximately 40 miles beyond the main gate to the NTS. Corrective Action Unit 551 is comprised of the four Corrective Action Sites (CASs) shown on Figure 1-1 and listed below: (1) 12-01-09, Aboveground Storage Tank and Stain; (2) 12-06-05, Muckpile; (3) 12-06-07, Muckpile; and (4) 12-06-08, Muckpile. Corrective Action Site 12-01-09 is located in Area 12 and consists of an above ground storage tank (AST) and associated stain. Corrective Action Site 12-06-05 is located in Area 12 and consists of a muckpile associated with the U12 B-Tunnel. Corrective Action Site 12-06-07 is located in Area 12 and consists of a muckpile associated with the U12 C-, D-, and F-Tunnels. Corrective Action Site 12-06-08 is located in Area 12 and consists of a muckpile associated with the U12 B-Tunnel. In keeping with common convention, the U12B-, C-, D-, and F-Tunnels will be referred to as the B-, C-, D-, and F-Tunnels. The corrective action investigation (CAI) will include field inspections, radiological surveys, and sampling of media, where appropriate. Data will also be obtained to support waste management decisions.

David A. Strand

2004-06-01T23:59:59.000Z

429

Corrective Action Investigation Plan for Corrective Action Unit 551: Area 12 Muckpiles, Nevada Test Site, Nevada, Rev. No. 0  

SciTech Connect (OSTI)

This Corrective Action Investigation Plan (CAIP) contains project-specific information including facility descriptions, environmental sample collection objectives, and criteria for conducting site investigation activities at Corrective Action Unit (CAU) 551, Area 12 muckpiles, Nevada Test Site (NTS), Nevada. This CAIP has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996) that was agreed to by the State of Nevada, the U.S. Department of Energy (DOE), and the U.S. Department of Defense. Corrective Action Unit 551 is located in Area 12 of the NTS, which is approximately 110 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Area 12 is approximately 40 miles beyond the main gate to the NTS. Corrective Action Unit 551 is comprised of the four Corrective Action Sites (CASs) shown on Figure 1-1 and listed below: (1) 12-01-09, Aboveground Storage Tank and Stain; (2) 12-06-05, Muckpile; (3) 12-06-07, Muckpile; and (4) 12-06-08, Muckpile. Corrective Action Site 12-01-09 is located in Area 12 and consists of an above ground storage tank (AST) and associated stain. Corrective Action Site 12-06-05 is located in Area 12 and consists of a muckpile associated with the U12 B-Tunnel. Corrective Action Site 12