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Note: This page contains sample records for the topic "materials clsm reported" from the National Library of EnergyBeta (NLEBeta).
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1

WSRC-TR-97-0100 Controlled Low Strength Materials (CLSM), Reported...  

Office of Scientific and Technical Information (OSTI)

protection and in stilling basins below dam spillways are often filled with CLSM to hold rock pieces in place and prevent erosion. Flexible fabric mattresses used along...

2

CLSM bleed water reduction test results  

SciTech Connect (OSTI)

Previous testing by BSRI/SRTC/Raytheon indicated that the CLSM specified for the Tank 20 closure generates about 6 gallons (23 liters) of bleed water per cubic yard of material (0.76 m3).1 This amount to about 10 percent of the total mixing water. HLWE requested that the CLSM mix be optimized to reduce bleed water while maintaining flow. Elimination of bleed water from the CLSM mix specified for High-Level Waste Tank Closure will result in waste minimization, time savings and cost savings. Over thirty mixes were formulated and evaluated at the on-site Raytheon Test Laboratory. Improved low bleed water CLSM mixes were identified. Results are documented in this report.

Langton, C.A. [Westinghouse Savannah River Company, Aiken, SC (United States); Rajendran, N. [Bechtel Savannah River Company, Aiken, SC (United States)

1997-04-21T23:59:59.000Z

3

High Performance Zero-Bleed CLSM/Grout Mixes for High-Level Waste Tank Closures Strategic Research and Development - FY99 Report  

SciTech Connect (OSTI)

The overall objective of this program, SRD-99-08, was to design and test suitable materials, which can be used to close high-level waste tanks at SRS. Fill materials can be designed to perform several functions including chemical stabilization and/or physical encapsulation of incidental waste so that the potential for transport of contaminants into the environment is reduced. Also they are needed to physically stabilize the void volume in the tanks to prevent/minimize future subsidence and inadvertent intrusion. The intent of this work was to develop a zero-bleed soil CLSM (ZBS-CLSM) and a zero-bleed concrete mix (ZBC) which meet the unique placement and stabilization/encapsulation requirements for high-level waste tank closures. These mixes in addition to the zero-bleed CLSM mixes formulated for closure of Tanks 17-F and 20-F provide design engineers with a suite of options for specifying materials for future tank closures.

Langton, C.A.

2000-08-11T23:59:59.000Z

4

WSRC-TR-97-0100 Controlled Low Strength Materials (CLSM), Reported by ACI  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism inS-4500IIVasudhaSurface.Laboratory30,WP-07 power rates

5

Materials Department Annual Report 1992  

E-Print Network [OSTI]

Materials Department Annual Report 1992 Published by the Materials Department Risø National and stone by Chr. Dahlgaard Larsen Materials Department Risø National Laboratory, Roskilde, Denmark Tel.: +45 46 77 46 77 Fax: +4542351173 #12;Abstract Selected activities ot the Materials Department at Riso

6

Materials Department Annual Report 1991  

E-Print Network [OSTI]

Materials Department Annual Report 1991 Published by the Materials Department Risø National, iron and stone by Chr. Dahlgaard Larsen Materials Department Risø National Laboratory, Roskilde, Denmark Tel.: +45 42 37 12 12 Fax: + 45 42 35 11 73 #12;Abstract Selected activities of the Materials

7

Thermoelectric materials development. Final report  

SciTech Connect (OSTI)

A systematic search for advanced thermoelectric materials was initiated at JPL several years ago to evaluate candidate materials which includes consideration of the following property attributes: (1) semiconducting properties; (2) large Seebeck coefficient; (3) high carrier mobility and high electrical conductivity; (4) low lattice thermal conductivity; and (5) chemical stability and low vapor pressure. Through this candidate screening process, JPL identified several families of materials as promising candidates for improved thermoelectric materials including the skutterudite family. There are several programs supporting various phases of the effort on these materials. As part of an ongoing effort to develop skutterudite materials with lower thermal conductivity values, several solid solutions and filled skutterudite materials were investigated under the effort sponsored by DOE. The efforts have primarily focused on: (1) study of existence and properties of solid solutions between the binary compounds CoSb{sub 3} and IrSb{sub 3}, and RuSb{sub 2}Te, and (2) CeFe{sub 4{minus}x}Sb{sub 12} based filled compositions. For the solid solutions, the lattice thermal conductivity reduction was expected to be reduced by the introduction of the Te and Ru atoms while in the case of CeFe{sub 4{minus}x}Ru{sub x}Sb{sub 12} based filled compositions. For the solid solutions, the lattice thermal conductivity reduction was expected to be reduced by the introduction of the Te and Ru atoms while in the case of CeFe{sub 4{minus}x}Ru{sub x}Sb{sub 12} filled compositions, the reduction would be caused by the rattling of Ce atoms located in the empty voids of the skutterudite structure and the substitution of Fe for Ru. The details of the sample preparation and characterization of their thermoelectric properties are reported in this report.

Fleurial, J.P.; Caillat, T.; Borshchevsky, A.

1998-09-01T23:59:59.000Z

8

DWPF MATERIALS EVALUATION SUMMARY REPORT  

SciTech Connect (OSTI)

To better ensure the reliability of the Defense Waste Processing Facility (DWPF) remote canyon process equipment, a materials evaluation program was performed as part of the overall startup test program. Specific test programs included FA-04 ('Process Vessels Erosion/Corrosion Studies') and FA-05 (melter inspection). At the conclusion of field testing, Test Results Reports were issued to cover the various test phases. While these reports completed the startup test requirements, DWPF-Engineering agreed to compile a more detailed report which would include essentially all of the materials testing programs performed at DWPF. The scope of the materials evaouation programs included selected equipment from the Salt Process Cell (SPC), Chemical Process Cell (CPC), Melt Cell, Canister Decon Cell (CDC), and supporting facilities. The program consisted of performing pre-service baseline inspections (work completed in 1992) and follow-up inspections after completion of the DWPF cold chemical runs. Process equipment inspected included: process vessels, pumps, agitators, coils, jumpers, and melter top head components. Various NDE (non-destructive examination) techniques were used during the inspection program, including: ultrasonic testing (UT), visual (direct or video probe), radiography, penetrant testing (PT), and dimensional analyses. Finally, coupon racks were placed in selected tanks in 1992 for subsequent removal and corrosion evaluation after chemical runs.

Gee, T.; Chandler, G.; Daugherty, W.; Imrich, K.; Jankins, C.

1996-09-12T23:59:59.000Z

9

Materials Sciences Division 1990 annual report  

SciTech Connect (OSTI)

This report is the Materials Sciences Division`s annual report. It contains abstracts describing materials research at the National Center for Electron Microscopy, and for research groups in metallurgy, solid-state physics, materials chemistry, electrochemical energy storage, electronic materials, surface science and catalysis, ceramic science, high tc superconductivity, polymers, composites, and high performance metals.

Not Available

1990-12-31T23:59:59.000Z

10

Materials Sciences Division 1990 annual report  

SciTech Connect (OSTI)

This report is the Materials Sciences Division's annual report. It contains abstracts describing materials research at the National Center for Electron Microscopy, and for research groups in metallurgy, solid-state physics, materials chemistry, electrochemical energy storage, electronic materials, surface science and catalysis, ceramic science, high tc superconductivity, polymers, composites, and high performance metals.

Not Available

1990-01-01T23:59:59.000Z

11

New laser materials: Final report  

SciTech Connect (OSTI)

In the Interim Report No. 1, it was reported that the fluorescence lifetime (greater than or equal to 750..mu..s) in Nd doped Y(PO/sub 3/)/sub 3/ was longer by a factor of three as compared to YAG. This means potentially three times as much energy storage and consequently more efficient for flashlamp pumping. It also makes diode pumping easier. In addition, since the Y site is octahedrally coordinated, there is a possibility of energy transfer using Cr as the sensitizing element. As suggested by W. Krupke, we decided to explore the trivalent cation metaphosphates systematically. The compounds investigated can be represented by the general formula A(PO/sub 3/)/sub 3/ where A = Y, Lu, In, Sc, GA and Al. The object is to study the fluorescence characteristics of Nd and Cr as well as the effectiveness of energy transfer from Cr to Nd. In addition, we also investigated other possible laser host crystals, notably CaMgSi/sub 2/O/sub 6/ (diopside), LaBO/sub 3/ and La(BO/sub 2/)/sub 3/. Results on these materials will also be discussed.

Not Available

1986-10-01T23:59:59.000Z

12

2014 Annual Merit Review Results Report - Materials Technologies...  

Energy Savers [EERE]

Materials Technologies: Propulsion Materials 2014 Annual Merit Review Results Report - Materials Technologies: Propulsion Materials Merit review of DOE Vehicle Technologies...

13

Materials Research Department Annual Report 2003  

E-Print Network [OSTI]

Materials Research Department Annual Report 2003 Risø National Laboratory April 2004 Risø-R-1451 in Four Dimensions 8-11 Composites and Materials Mechanics 12-15 Nano- and Microstructures in Materials 16-19 Fuel Cells and Materials Chemistry 20-23 24th Risø International Symposium 24 Finances 25 Staff 26

14

Hydrogen Materials Compatibility - FY 2007 Final Report  

SciTech Connect (OSTI)

This report describes the work conducted in FY07 on the Hydrogen Materials Compatibility program that involves PNNL and ORNL researchers.

Holbery, Jim; Henager, Charles H.; Pitman, Stan G.; Ryan, Joseph V.

2007-10-01T23:59:59.000Z

15

Materials Research Department Annual Report 2001  

E-Print Network [OSTI]

Materials Research Department Annual Report 2001 P u b l i s h e d b y t h e M a t e r i a l s R e 1-3 Scientific work 4-24 A multiscale view 4-5 Metal structures 6-7 Materials mechanics 8-9 Composite materials 10-11 Nanostructured materials 12-13 The fuel cell programme 14-17 Biological physics 18

16

REPORT NO. 5 background material  

E-Print Network [OSTI]

of atmospheric testing of nuclear weapons in 1961 and 1962 the question arose as to the possible need for protec from such events as: (1) an industrial accident, possibly involving a nuclear reactor or a nuclear fuel processing plant, and (2) release of radioactive materials from the detonation of nuclear weapons or other

17

Materials Research Department Annual Report 2002  

E-Print Network [OSTI]

Materials Research Department Annual Report 2002 Risø National Laboratory May 2003 Risø-R-1404 (EN- cruitment of many new employees during the year, especially within our solid oxide fuel cell research in the Danish research system. Although the annual report covers 2002, we felt it natural that the annual report

18

CONTROLLED LOW-STRENGTH MATERIAL (CLSM) PRODUCED WITH HIGH-LIME FLY ASH  

E-Print Network [OSTI]

by the Detroit Edison Company, Detroit, Michigan, and Kuhlman Corp., Toledo, Ohio in the 1970s. The investigation

Wisconsin-Milwaukee, University of

19

FY 2009 Progress Report for Lightweighting Materials - 5. Automotive...  

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

9 Progress Report for Lightweighting Materials - 5. Automotive Metals - Steel FY 2009 Progress Report for Lightweighting Materials - 5. Automotive Metals - Steel The primary...

20

FY 2009 Progress Report for Lightweighting Materials - 3. Automotive...  

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

9 Progress Report for Lightweighting Materials - 3. Automotive Metals - Cast FY 2009 Progress Report for Lightweighting Materials - 3. Automotive Metals - Cast The primary...

Note: This page contains sample records for the topic "materials clsm reported" 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

2014 Annual Merit review Results Report - Materials Technologies...  

Energy Savers [EERE]

review Results Report - Materials Technologies 2014 Annual Merit review Results Report - Materials Technologies Merit review of DOE Vehicle Technologies research activities...

22

2012 Annual Merit Review Results Report - Materials Technologies...  

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

- Materials Technologies: Propulsion Materials 2012 Annual Merit Review Results Report - Hybrid Vehicle Systems Technologies 2012 Annual Merit Review Results Report - Introduction...

23

MATERIALS AND MOLECULAR RESEARCH DIVISION Annual Report 1977.  

E-Print Network [OSTI]

ld Strength of Sialon-Type Materials . . High-Temperatureand Reports . . . . . . . . . . . C. Materials Chemistry 1.VIII. APPENDICES A. Materials and Molecular Research

Authors, Various

2011-01-01T23:59:59.000Z

24

Chemistry and materials science research report  

SciTech Connect (OSTI)

The research reported here in summary form was conducted under the auspices of Weapons-Supporting Research (WSR) and Institutional Research and Development (IR D). The period covered is the first half of FY90. The results reported here are for work in progress; thus, they may be preliminary, fragmentary, or incomplete. Research in the following areas are briefly described: energetic materials, tritium, high-Tc superconductors, interfaces, adhesion, bonding, fundamental aspects of metal processing, plutonium, synchrotron-radiation-based materials science, photocatalysis on doped aerogels, laser-induced chemistry, laser-produced molecular plasmas, chemistry of defects, dta equipment development, electronic structure study of the thermodynamic and mechanical properties of Al-Li Alloys, and the structure-property link in sub-nanometer materials.

Not Available

1990-05-31T23:59:59.000Z

25

Annual report, Materials Science Branch, FY 1992  

SciTech Connect (OSTI)

This report summarizes the progress of the Materials Science Branch of the National Renewable Energy Laboratory (NREL) from October 1, 1991, through September 30, 1992. Six technical sections of the report cover these main areas of NREL`s in-house research: Crystal Growth, Amorphous Silicon, III-V High-Efficiency Photovoltaic Cells, Solid State Theory, Solid State Spectroscopy, and Program Management. Each section explains the purpose and major accomplishments of the work in the context of the US Department of Energy`s National Photovoltaic Research Program plans.

Padilla, S. [ed.

1993-10-01T23:59:59.000Z

26

Material Balance Report | Department of Energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustion | Department of EnergyDevelopment Accident TolerantDepartment ofMaterial Balance Report

27

High Temperature Materials Laboratory third annual report  

SciTech Connect (OSTI)

The High Temperature Materials Laboratory has completed its third year of operation as a designated DOE User Facility at the Oak Ridge National Laboratory. Growth of the user program is evidenced by the number of outside institutions who have executed user agreements since the facility began operation in 1987. A total of 88 nonproprietary agreements (40 university and 48 industry) and 20 proprietary agreements (1 university, 19 industry) are now in effect. Sixty-eight nonproprietary research proposals (39 from university, 28 from industry, and 1 other government facility) and 8 proprietary proposals were considered during this reporting period. Research projects active in FY 1990 are summarized.

Tennery, V.J.; Foust, F.M.

1990-12-01T23:59:59.000Z

28

NUCLEAR MATERIALS PROGRESS REPORTS FOR 1980  

E-Print Network [OSTI]

Ceramics", Progress in Material Science 21, 307 (1976}. S. -heating techniques in material processing. Thermal analysisIrreversible Thermodynamics in Materials Problems", in Mass

Olander, D.R.

2010-01-01T23:59:59.000Z

29

Materials Considerations and Data Base APEX Interim Report November, 1999  

E-Print Network [OSTI]

Materials Considerations and Data Base APEX Interim Report November, 1999 13-1 CHAPTER 13: MATERIALS CONSIDERATIONS AND DATA BASE Contributors Lead Author: S.J. Zinkle S. Majumdar N.M. Ghoniem S. Sharafat. #12;Materials Considerations and Data Base APEX Interim Report November, 1999 13-2 13. MATERIALS

California at Los Angeles, University of

30

AMIS-Training Material iReport Training Part 2  

E-Print Network [OSTI]

AMIS- Training Material iReport Training ­Part 2 (iReport-3.0.0) Topic: Parameters · Open a report- Training Material · Open the `Document structure' Page 2 of 7 6/27/2008 Institutional Research and Planning University of Nebraska-Lincoln #12;AMIS- Training Material · Right click on `Parameters' > Add > Parameter

Farritor, Shane

31

Chemistry and materials science progress report, FY 1994  

SciTech Connect (OSTI)

Research is reported in the areas of surface science, fundamentals of the physics and processing of metals, energetic materials, transactinide materials and properties and other indirectly related areas of weapons research.

NONE

1995-07-01T23:59:59.000Z

32

NUCLEAR MATERIALS RESEARCH PROGRESS REPORTS FROM 1977  

E-Print Network [OSTI]

Chemical Effects of Thermonuclear Plasma Interactions Withfor Controlled Thermonuclear Reactor (CTR), USAEC Report LA-

Olander, D.R.

2012-01-01T23:59:59.000Z

33

FY 2009 Progress Report for Lightweighting Materials - 6. Automotive...  

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

2008 Progress Report for Lightweighting Materials - 6. Automotive Metals-Crosscutting Magnesium Front End Research and Development AMD 604 Magnesium Front End Development (AMD 603...

34

Materials and Molecular Research Division: Annual report, 1986  

SciTech Connect (OSTI)

Research activities are reported under the following headings: materials sciences, chemical sciences, nuclear sciences, fossil energy, energy storage systems, and work for others. (DLC)

Phillips, N.E.; Muller, R.H.; Peterson, C.V.

1987-07-01T23:59:59.000Z

35

2011 Annual Merit Review Results Report - Materials Technologies...  

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

Fuels Technologies 2010 DOE EERE Vehicle Technologies Program Merit Review - Propulsion Materials 2011 Annual Merit Review Results Report - Hybrid and Vehicle Systems Technologies...

36

2011 Annual Progress Report for Lightweighting Materials  

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

counties throughout Mississippi in an effort to inspire young students' interest in science and engineering. 2-70 Activity and Developments Task 1 - Multiscale Material...

37

NUCLEAR MATERIALS RESEARCH PROGRESS REPORTS FOR 1979  

E-Print Network [OSTI]

Chemical E f f e c t s of Thermonuclear Plasma I n t e r a cfor Controlled Thermonuclear Reactor (CTR), USAEC Report LA

Olander, D.R.

2010-01-01T23:59:59.000Z

38

Nuclear Materials Management and Safeguards System Reporting and Data Submission  

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

The manual provides clear and detailed instructions and procedures for documenting and reporting data submissions for nuclear materials transactions, inventories, and material balances to the Nuclear Materials Management and Safeguards System (NMMSS). Cancels DOE 5633.3B. Canceled by DOE M 474.1-2A.

1998-02-10T23:59:59.000Z

39

Materials and Molecular Research Division annual report 1983  

SciTech Connect (OSTI)

Progress is reported in the following fields: materials sciences (metallurgy and ceramics, solid-state physics, materials chemistry), chemical sciences (fundamental interactions, processes and techniques), actinide chemistry, fossil energy, electrochemical energy storage systems, superconducting magnets, semiconductor materials and devices, and work for others. (DLC)

Searcy, A.W.; Muller, R.H.; Peterson, C.V.

1984-07-01T23:59:59.000Z

40

SANDIA CONTRACTORS REPORT FATIGUE OF COMPOSITE MATERIALS AND  

E-Print Network [OSTI]

SANDIA CONTRACTORS REPORT FATIGUE OF COMPOSITE MATERIALS AND SUBSTRUCTURES FOR WIND TURBINE BLADES Abstract ThisreportpresentsthemajorfindingsoftheMontanaStateUniversityCompositeMaterialsFatigue Program from 1997 to 2001, and is intended to be used in conjunction with the DOE/MSU Composite Materials

Note: This page contains sample records for the topic "materials clsm reported" 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

Geothermal Materials Development. Annual report FY 1991  

SciTech Connect (OSTI)

Advances in the development of new materials, the commercial availabilities of which are essential for the attainment of Hydrothermal Category Level I and II Objectives, continue to be made in the Geothermal Materials Development Project. Many successes have already been accrued and the results used commercially. In FY 1991, utility company sponsored ``full cost`` recovery programs based upon materials technology developed in this project were initiated on topics such as condensing heat exchangers, high temperature composites for utility vaults used in district heating systems, and corrosion resistant coatings for use in oil-fired electric generating processes. In FY 1991 the DOE/GD-sponsored R&D project was focused on reducing well drilling, fluid transport and energy conversion costs. Specific activities being performed included lightweight CO{sub 2}- resistant well cements, chemical systems for lost circulation control, thermally conductive and scale resistant protective linear systems, corrosion mitigation in process components at The Geysers, and elastomer-metal bonding systems needed for use in high temperature well drilling and safety related applications.

Kukacka, L.E.

1991-12-01T23:59:59.000Z

42

Geothermal Materials Development, Annual Report FY 1991  

SciTech Connect (OSTI)

Advances in the development of new materials, the commercial availabilities of which are essential for the attainment of Hydrothermal Category Level I and II Objectives, continue to be made in the Geothermal Materials Development Project. Many successes have already been accrued and the results used commercially. In FY 1991, utility company sponsored full cost'' recovery programs based upon materials technology developed in this project were initiated on topics such as condensing heat exchangers, high temperature composites for utility vaults used in district heating systems, and corrosion resistant coatings for use in oil-fired electric generating processes. In FY 1991 the DOE/GD-sponsored R D project was focused on reducing well drilling, fluid transport and energy conversion costs. Specific activities being performed included lightweight CO{sub 2}- resistant well cements, chemical systems for lost circulation control, thermally conductive and scale resistant protective linear systems, corrosion mitigation in process components at The Geysers, and elastomer-metal bonding systems needed for use in high temperature well drilling and safety related applications.

Kukacka, L.E.

1991-12-01T23:59:59.000Z

43

Advanced lubrication systems and materials. Final report  

SciTech Connect (OSTI)

This report described the work conducted at the National Institute of Standards and Technology under an interagency agreement signed in September 1992 between DOE and NIST for 5 years. The interagency agreement envisions continual funding from DOE to support the development of fuel efficient, low emission engine technologies in terms of lubrication, friction, and wear control encountered in the development of advanced transportation technologies. However, in 1994, the DOE office of transportation technologies was reorganized and the tribology program was dissolved. The work at NIST therefore continued at a low level without further funding from DOE. The work continued to support transportation technologies in the development of fuel efficient, low emission engine development. Under this program, significant progress has been made in advancing the state of the art of lubrication technology for advanced engine research and development. Some of the highlights are: (1) developed an advanced high temperature liquid lubricant capable of sustaining high temperatures in a prototype heat engine; (2) developed a novel liquid lubricant which potentially could lower the emission of heavy duty diesel engines; (3) developed lubricant chemistries for ceramics used in the heat engines; (4) developed application maps for ceramic lubricant chemistry combinations for design purpose; and (5) developed novel test methods to screen lubricant chemistries for automotive air-conditioning compressors lubricated by R-134a (Freon substitute). Most of these findings have been reported to the DOE program office through Argonne National Laboratory who manages the overall program. A list of those reports and a copy of the report submitted to the Argonne National Laboratory is attached in Appendix A. Additional reports have also been submitted separately to DOE program managers. These are attached in Appendix B.

Hsu, S.

1998-05-07T23:59:59.000Z

44

Contribution to Fusion Materials Semiannual Report  

SciTech Connect (OSTI)

The objectives of this work are the following: (1) The application of micro and mesoscale modeling techniques to study dislocation properties in ferritic and W-based materials; and (2) The development of computational models and tools to study damage accumulation in >1 dpa (fusion-like) conditions, both for Fe and W-based alloys. The high-temperature strength of structural ferritic alloys (ferritic/martensitic steels, ODS steels, bcc refractory alloys) hinges on the thermal stability of second phase particles and their interactions with dislocations. Irradiation damage can modify the structure and stability of both the particles and dislocations, particularly by the introduction of gas atoms, point defects and point defect clusters. The three aspects of materials strength that we are studying are: (a) Computation of dislocation mobility functions (stress-velocity relations) as a function of temperature and dislocation character. This will be done via molecular dynamics (MD) simulations of single dislocation motion under applied shear stress. This is a fundamental input to dislocation dynamics (DD) simulations and also provides fundamental insights into the high-temperature plastic behavior of ferritic materials. (b) Simulations of dislocation-obstacle interactions using MD and DD. This subtask includes simulating the effect on dislocation glide of precipitates (e.g., {alpha}' Cr precipitates), ODS particles, and irradiation induced defect clusters (e.g. voids, dislocation loops, etc.). (c) Implementation of this information (dislocation mobilities and dislocation-defect interaction rules) into DD codes that will allow us to study plasticity of single crystals Fe alloys under relevant irradiation conditions.

Marian, J; Meier, W

2012-02-24T23:59:59.000Z

45

Energy Materials and Processes Workshop Report | EMSL  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-Series toESnet4: Networking for37 EastEIA-64A AnnualEnergy Materials and

46

Energy Materials Coordinating Committee, fiscal year 1997. Annual technical report  

SciTech Connect (OSTI)

The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department`s materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. This report summarizes EMaCC activities for FY 1997 and describes the materials research programs of various offices and divisions within the Department.

NONE

1998-07-31T23:59:59.000Z

47

MATERIALS AND MOLECULAR RESEARCH DIVISION ANNUAL REPORT 1979  

E-Print Network [OSTI]

will also be conducted in shale oil product material. 1979Publications and Reports d. Oil Shale Retort Components A.in Simulated In-Situ Oil Shale Retorts Research Plans for

Authors, Various

2013-01-01T23:59:59.000Z

48

Sandia National Laboratories, California Hazardous Materials Management Program annual report.  

SciTech Connect (OSTI)

The annual program report provides detailed information about all aspects of the Sandia National Laboratories, California (SNL/CA) Hazardous Materials Management Program. It functions as supporting documentation to the SNL/CA Environmental Management System Program Manual. This program annual report describes the activities undertaken during the calender past year, and activities planned in future years to implement the Hazardous Materials Management Program, one of six programs that supports environmental management at SNL/CA.

Brynildson, Mark E.

2011-02-01T23:59:59.000Z

49

Strategic special nuclear material inventory differences. Semi-annual report  

SciTech Connect (OSTI)

This report provides and explains the generally small differences between the amounts of nuclear materials charged to DOE facilities and the amounts that could be physically inventoried. These Inventory Differences, previously called Material Unaccounted For (MUF), are being publicly released on a semiannual basis. This report covers data for the period from October 1, 1978, through March 31, 1979, and includes accounting corrections for data from earlier periods.

None

1980-01-01T23:59:59.000Z

50

Materials and Molecular Research Division annual report 1980  

SciTech Connect (OSTI)

Progress made in the following research areas is reported: materials sciences (metallurgy and ceramics, solid state physics, materials chemistry); chemical sciences (fundamental interactions, processes and techniques); nuclear sciences; fossil energy; advanced isotope separation technology; energy storage; magnetic fusion energy; and nuclear waste management.

Not Available

1981-06-01T23:59:59.000Z

51

Nuclear materials 1993 annual report. Volume 8, No. 2  

SciTech Connect (OSTI)

This annual report of the US Nuclear Regulatory Commission`s Office for Analysis and Evaluation of Operational Data (AEOD) describes activities conducted during 1993. The report is published in two parts. NUREG-1272, Vol. 8, No. 1, covers power reactors and presents an overview of the operating experience of the nuclear power industry from the NRC perspective, including comments about the trends of some key performance measures. The report also includes the principal findings and issues identified in AEOD studies over the past year and summarizes information from such sources as licensee event reports, diagnostic evaluations, and reports to the NRC`s Operations Center. NUREG-1272, Vol. 8, No. 2, covers nuclear materials and presents a review of the events and concerns during 1993 associated with the use of licensed material in nonreactor applications, such as personnel overexposures and medical misadministrations. Note that the subtitle of No. 2 has been changed from ``Nonreactors`` to ``Nuclear Materials.`` Both reports also contain a discussion of the Incident Investigation Team program and summarize both the Incident Investigation Team and Augmented Inspection Team reports. Each volume contains a list of the AEOD reports issued from 1980 through 1993.

NONE

1995-05-01T23:59:59.000Z

52

Materials  

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

2 MAG LAB REPORTS Volume 18 No. 1 CONDENSED MATTER SCIENCE Technique development, graphene, magnetism & magnetic materials, topological insulators, quantum fl uids & solids,...

53

Materials and Chemical Sciences Division annual report 1989  

SciTech Connect (OSTI)

This report describes research conducted at Lawrence Berkeley Laboratories, programs are discussed in the following topics: materials sciences; chemical sciences; fossil energy; energy storage systems; health and environmental sciences; exploratory research and development funds; and work for others. A total of fifty eight programs are briefly presented. References, figures, and tables are included where appropriate with each program.

Not Available

1990-07-01T23:59:59.000Z

54

Materials and Molecular Research Division annual report 1982  

SciTech Connect (OSTI)

This report is divided into: materials sciences, chemical sciences, nuclear sciences, fossil energy, advanced isotope separation technology (AISI), energy storage, magnetic fusion energy (MFE), nuclear waste management, and work for others (WFO). Separate abstracts have been prepared for all except AIST, MFE, and WFO. (DLC)

Not Available

1983-05-01T23:59:59.000Z

55

Materials and Molecular Research Division. Annual report 1981  

SciTech Connect (OSTI)

Progress is reported in the areas of materials sciences, chemical sciences, nuclear sciences, fossil energy, advanced (laser) isotope separation technology, energy storage, superconducting magnets, and nuclear waste management. Work for others included phase equilibria for coal gasification products and ..beta..-alumina electrolytes for storage batteries. (DLC)

Not Available

1982-08-01T23:59:59.000Z

56

Chemistry and Materials Science Department annual report, 1988--1989  

SciTech Connect (OSTI)

This is the first annual report of the Chemistry & Materials Science (C&MS) Department. The principal purpose of this report is to provide a concise summary of our scientific and technical accomplishments for fiscal years 1988 and 1989. The report is also tended to become part of the archival record of the Department`s activities. We plan to publish future editions annually. The activities of the Department can be divided into three broad categories. First, C&MS staff are assigned by the matrix system to work directly in a program. These programmatic assignments typically involve short deadlines and critical time schedules. A second category is longer-term research and development in technologies important to Laboratory programs. The focus and direction of this technology-base work are generally determined by programmatic needs. Finally, the Department manages its own research program, mostly long-range in outlook and basic in orientation. These three categories are not mutually exclusive but form a continuum of technical activities. Representative examples of all three are included in this report. The principal subject matter of this report has been divided into six sections: Innovations in Analysis and Characterization, Advanced Materials, Metallurgical Science and Technology, Surfaces and Interfaces, Energetic Materials and Chemical Synthesis, and Energy-Related Research and Development.

Borg, R.J.; Sugihara, T.T.; Cherniak, J.C.; Corey, C.W. [eds.

1989-12-31T23:59:59.000Z

57

Advanced Industrial Materials (AIM) Program: Annual progress report FY 1995  

SciTech Connect (OSTI)

In many ways, the Advanced Industrial Materials (AIM) Program underwent a major transformation in Fiscal Year 1995 and these changes have continued to the present. When the Program was established in 1990 as the Advanced Industrial Concepts (AIC) Materials Program, the mission was to conduct applied research and development to bring materials and processing technologies from the knowledge derived from basic research to the maturity required for the end use sectors for commercialization. In 1995, the Office of Industrial Technologies (OIT) made radical changes in structure and procedures. All technology development was directed toward the seven ``Vision Industries`` that use about 80% of industrial energy and generated about 90% of industrial wastes. The mission of AIM has, therefore, changed to ``Support development and commercialization of new or improved materials to improve productivity, product quality, and energy efficiency in the major process industries.`` Though AIM remains essentially a National Laboratory Program, it is essential that each project have industrial partners, including suppliers to, and customers of, the seven industries. Now, well into FY 1996, the transition is nearly complete and the AIM Program remains reasonably healthy and productive, thanks to the superb investigators and Laboratory Program Managers. This Annual Report for FY 1995 contains the technical details of some very remarkable work by the best materials scientists and engineers in the world. Areas covered here are: advanced metals and composites; advanced ceramics and composites; polymers and biobased materials; and new materials and processes.

NONE

1996-04-01T23:59:59.000Z

58

Admixture enhanced controlled low-strength material for direct underwater injection with minimal cross-contamination  

SciTech Connect (OSTI)

Commercially available admixtures have been developed for placing traditional concrete products under water. This paper evaluates adapting anti-washout admixture (AWA) and high range water reducing admixture (HRWRA) products to enhance controlled low-strength materials (CLSMs) for underwater placement. A simple experimental scale model (based on dynamic and geometric similitude) of typical grout pump emplacement equipment has been developed to determine the percentage of cementing material washed out. The objective of this study was to identify proportions of admixtures and underwater CLSM emplacement procedures which would minimize the cross-contamination of the displaced water while maintaining the advantages of CLSM. Since the displaced water from radioactively contaminated systems must be subsequently treated prior to release to the environment, the amount of cross-contamination is important for cases in which cementing material could form hard sludges in a water treatment facility and contaminate the in-place CLSM stabilization medium.

Hepworth, H.K.; Davidson, J.S.; Hooyman, J.L.

1997-03-01T23:59:59.000Z

59

Chemistry and Materials Science Directorate 2005 Annual Report  

SciTech Connect (OSTI)

In 1952, we began laboratory operations in the barracks building of the Naval Air Station with approximately 50 employees. Today, the Chemistry and Materials Science (CMS) Directorate is a major organization at the Lawrence Livermore National Laboratory with more than 500 employees who continue to contribute to our evolving national security mission. For more than half a century, the mission of the Laboratory revolved primarily around nuclear deterrence and associated defense technologies. Today, Livermore supports a broad-based national security mission, and our specialized capabilities increasingly support emerging missions in human health and energy security. In the future, CMS will play a significantly expanded role in science and technology at the intersection of national security, energy and environment, and health. Our world-class workforce will provide the science and technology base for radically innovative materials to our programs and sponsors. Our 2005 Annual Report describes how our successes and breakthroughs follow a path set forward by our strategic plan and four organizing research themes, each with key scientific accomplishments by our staff and collaborators. Organized into two major sections-research themes and dynamic teams, this report focuses on achievements arising from earlier investments that address future challenges. The research presented in this annual report gives substantive examples of how we are proceeding in each of these four theme areas and how they are aligned with our national security mission. Research Themes: (1) Materials Properties and Performance under Extreme Conditions--We are developing ultrahard nanocrystalline metals, exploring the properties of nanotubes when exposed to very high temperatures, and engineering stronger materials to meet future needs for materials that can withstand extreme conditions. (2) Chemistry under Extreme Conditions and Chemical Engineering to Support National-Security Programs--Our recent discovery of a new source of coherent light adds a new tool to an array of methods we use to more fully understand the properties of materials. Insights into the early stages of polymer crystallization may lead to new materials for our national-security mission and private industry. (3) Science Supporting National Objectives at the Intersection of Chemistry, Materials Science, and Biology--We are improving drug binding for cancer treatment through the use of new tools that are helping us characterize protein-antibody interactions. By probing proteins and nucleic acids, we may gain an understanding of Alzheimer's, Mad Cow, and other neurodegenerative diseases. (4) Applied Nuclear Science for Human Health and National Security--Our work with cyanobacteria is leading to a fuller understanding of how these microorganisms affect the global carbon cycle. We are also developing new ways to reduce nuclear threats with better radiation detectors. Dynamic Teams: The dynamic teams section illustrates the directorate's organizational structure that supports a team environment across disciplinary and institutional boundaries. Our three divisions maintain a close relationship with Laboratory programs, working with directorate and program leaders to ensure an effective response to programmatic needs. CMS's divisions are responsible for line management and leadership, and together, provide us with the flexibility and agility to respond to change and meet program milestones. The three divisions are: Materials Science and Technology Division; Chemistry and Chemical Engineering Division; and Chemical Biology and Nuclear Science Division. By maintaining an organizational structure that offers an environment of collaborative problem-solving opportunities, we are able to nurture the discoveries and breakthroughs required for future successes. The dynamic teams section also presents the work of CMS's postdoctoral fellows, who bring to the Laboratory many of the most recent advances taking place in academic departments and provide a research stimulus to established research teams. Postdo

Diaz De La Rubia, T; Fluss, M J; Rath, K; Rennie, G; Shang, S; Kitrinos, G

2006-08-08T23:59:59.000Z

60

Glazing materials for solar and architectural applications. Final report  

SciTech Connect (OSTI)

This report summarizes five collaborative research projects on glazings performed by participants in Subtask C of IEA Solar Heating and Cooling Programme (SHC) Task 10, Materials Research and Testing. The projects include materials characterization, optical and thermal measurements, and durability testing of several types of new glazings Three studies were completed on electrochromic and dispersed liquid crystals for smart windows, and two were completed for low-E coatings and transparent insulation materials for more conventional window and wall applications. In the area of optical switching materials for smart windows, the group developed more uniform characterization parameters that are useful to determine lifetime and performance of electrochromics. The detailed optical properties of an Asahi (Japan) prototype electrochromic window were measured in several laboratories. A one square meter array of prototype devices was tested outdoors and demonstrated significant cooling savings compared to tinted static glazing. Three dispersed liquid crystal window devices from Taliq (USA) were evaluated. In the off state, these liquid crystal windows scatter light greatly. When a voltage of about 100 V ac is applied, these windows become transparent. Undyed devices reduce total visible light transmittance by only .25 when switched, but this can be increased to .50 with the use of dyed liquid crystals. A wide range of solar-optical and emittance measurements were made on low-E coated glass and plastic. Samples of pyrolytic tin oxide from Ford glass (USA) and multilayer metal-dielectric coatings from Interpane (Germany) and Southwall (USA) were evaluated. In addition to optical characterization, the samples were exposure-tested in Switzerland. The thermal and optimal properties of two different types of transparent insulation materials were measured.

Lampert, C.M. [ed.

1994-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "materials clsm reported" 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

MATERIALS AND MOLECULAR RESEARCH DIVISION, ANNUAL REPORT 1976  

E-Print Network [OSTI]

Stress Behavior of Superplastic Materials 5. Fe-Ni Cryogenicof Aluminum Silicate Materials Preparation of Spinel PowderCalCUlations for Bulk Materials and for Adsorbates on Transi

Authors, Various

2010-01-01T23:59:59.000Z

62

Feed Materials Production Center annual environmental report for calendar 1989  

SciTech Connect (OSTI)

The mission of the Department of Energy's (DOE) Feed Materials Production Center (FMPC) has been to process uranium for United States' defense programs. On July 10, 1989, the FMPC suspended production operations, but remains on standby for certain segments of production. The FMPC also manages the storage of some radioactive and hazardous materials. As part of its operations, the FMPC continuously monitors the environment to determine that it is operating within federal and state standards and guidelines regarding emission of radioactive and nonradioactive materials. Data collected from the FMPC monitoring program are used to calculate estimates of radiation dose for residents due to FMPC operations. For 1989, the estimate of dose through the air pathway, excluding radon, indicated that people in the area were exposed to less than 6% of the DOE guideline established to protect the public from radiation exposure. When radon emissions are included, the dose from FMPC operations during 1989 was less than 22% of the annual background radiation dose in the Greater Cincinnati area. This report is a summary of FMPC's environmental activities and monitoring program for 1989. An Environmental Compliance Self-Assessment presents the FMPC's efforts to comply with environmental regulations through June 1990. 44 refs., 48 figs.

Dugan, T.A.; Gels, G.L.; Oberjohn, J.S.; Rogers, L.K.

1990-10-01T23:59:59.000Z

63

Down Select Report of Chemical Hydrogen Storage Materials, Catalysts, and Spent Fuel Regeneration Processes - May 2008  

Fuel Cell Technologies Publication and Product Library (EERE)

Chemical Hydrogen Storage Center of Excellence FY2008 Second Quarter Milestone Report: Technical report describing assessment of hydrogen storage materials and progress towards meeting DOEs hydrogen

64

High Temperature Materials Interim Data Qualification Report FY 2011  

SciTech Connect (OSTI)

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

Nancy Lybeck

2011-08-01T23:59:59.000Z

65

Report on sodium compatibility of advanced structural materials.  

SciTech Connect (OSTI)

This report provides an update on the evaluation of sodium compatibility of advanced structural materials. The report is a deliverable (level 3) in FY11 (M3A11AN04030403), under the Work Package A-11AN040304, 'Sodium Compatibility of Advanced Structural Materials' performed by Argonne National Laboratory (ANL), as part of Advanced Structural Materials Program for the Advanced Reactor Concepts. This work package supports the advanced structural materials development by providing corrosion and tensile data from the standpoint of sodium compatibility of advanced structural alloys. The scope of work involves exposure of advanced structural alloys such as G92, mod.9Cr-1Mo (G91) ferritic-martensitic steels and HT-UPS austenitic stainless steels to a flowing sodium environment with controlled impurity concentrations. The exposed specimens are analyzed for their corrosion performance, microstructural changes, and tensile behavior. Previous reports examined the thermodynamic and kinetic factors involved in the purity of liquid sodium coolant for sodium reactor applications as well as the design, fabrication, and construction of a forced convection sodium loop for sodium compatibility studies of advanced materials. This report presents the results on corrosion performance, microstructure, and tensile properties of advanced ferritic-martensitic and austenitic alloys exposed to liquid sodium at 550 C for up to 2700 h and at 650 C for up to 5064 h in the forced convection sodium loop. The oxygen content of sodium was controlled by the cold-trapping method to achieve {approx}1 wppm oxygen level. Four alloys were examined, G92 in the normalized and tempered condition (H1 G92), G92 in the cold-rolled condition (H2 G92), G91 in the normalized and tempered condition, and hot-rolled HT-UPS. G91 was included as a reference to compare with advanced alloy, G92. It was found that all four alloys showed weight loss after sodium exposures at 550 and 650 C. The weight loss of the four alloys was comparable after sodium exposures at 550 C; the weight loss of ferritic-martensitic steels, G92 and G91 is more significant than that of austenitic stainless steel, HT-UPS after sodium exposures at 650 C. Sodium exposures up to 2700 h at 550 C had no significant influence on tensile properties, while sodium exposures up to 5064 h at 650 C dramatically lowered the tensile strengths of the four alloys. The ultimate tensile strength of H1 G92, H2 G92, and G91 ferritic-martensitic steels was reduced to as much as nearly half of its initial value after sodium exposures at 650 C. Though the uniform elongation was recovered to some extent, these three ferritic-martensitic steels showed considerable strain softening after sodium exposures. The yield stress of HT-UPS austenitic stainless steel increased, the ultimate tensile strength decreased, and the total elongation was reduced after sodium exposures at 650 C. The dynamic strain aging effect observed in the as-received HT-UPS specimens became less pronounced after sodium exposures at 650 C. Microstructural characterization of sodium-exposed specimens showed no appreciable surface deterioration or grain structure changes under an optical microscope, except for the H2 G92 steel, in which the martensite structure transformed to large grain ferrite after sodium exposures at 650 C. TEM observations of the sodium-exposed H2 G92 steel showed significant recrystallization after sodium exposure for 2700 h at 550 C, and transformation of martensite to ferrite and high density of precipitates in nearly dislocation-free matrix after sodium exposures at 650 C. Further microstructural analysis and evaluation of decarburization/carburization behavior is needed to understand the dramatic changes in the tensile strengths of advanced ferritic-martensitic and austenitic steels after sodium exposures at 650 C.

Li, M.; Natesan, K.; Momozaki, Y.; Rink, D.L.; Soppet, W.K.; Listwan, J.T. (Nuclear Engineering Division)

2012-07-09T23:59:59.000Z

66

MATERIALS AND MOLECULAR RESEARCH DIVISION. ANNUAL REPORT 1980  

E-Print Network [OSTI]

Staff Seminars in Metallurgy and Materials Science,University, Department of Metallurgy, Cleveland, OH, JuneMaterials Research," Metallurgy Division, Department of

Searcy, Alan W.

2010-01-01T23:59:59.000Z

67

UWM-CBU Concrete Materials Technology Series Program No. 72 Construction Demonstration for Use of Residuals and Reject Fibers  

E-Print Network [OSTI]

UWM-CBU Concrete Materials Technology Series Program No. 72 Construction Demonstration for Use of Residuals and Reject Fibers from Pulp and Paper Industry in Concrete and CLSM Center for By Milwaukee, WI 53201 MILWAUKEE, WI PERMIT NO. 864 UWM-CBU Concrete Materials Technology Series Program No. 72

Saldin, Dilano

68

Fusion materials semiannual progress report for period ending December 31, 1999  

SciTech Connect (OSTI)

This is the twenty-seventh in a series of semiannual technical progress reports on fusion materials. This report combines the full spectrum of research and development activities on both metallic and non-metallic materials with primary emphasis on the effects of the neutronic and chemical environment on the properties and performance of materials for in-vessel components.

Burn, G.

2000-03-01T23:59:59.000Z

69

Thermal and chemical degradation of inorganic membrane materials. Topical report  

SciTech Connect (OSTI)

This report describes the results of a literature review to evaluate the long-term thermal and chemical degradation of inorganic membranes that are being developed to separate gaseous products produced by the gasification or combustion of coal in fixed-, fluidized-, and entrained-bed gasifiers, direct coal-fired turbines, and pressurized-fluidized-bed combustors. Several impurities, such as H{sub 2}S, NH{sub 3}, SO{sub 2}, NO{sub x}, and trace metal compounds are generated during coal conversion, and they must be removed from the coal gas or the combustor flue gas to meet environmental standards. The use of membranes to separate these noxious gases is an attractive alternative to their removal by sorbents such as zinc titanate or calcium oxide. Inorganic membranes that have a high separation efficiency and exhibit both thermal and chemical stability would improve the economics of power generation from coal. The U.S. Department of Energy is supporting investigations to develop inorganic membranes for separating hydrogen from coal gas streams and noxious impurities from hot coal- and flue-gas streams. Membrane materials that have been investigated in the past include glass (silica), alumina, zirconia, carbon, and metals (Pd and Pt).

Krishnan, G.N.; Sanjurjo, A.; Wood, B.J.; Lau, K.H.

1994-04-01T23:59:59.000Z

70

Special Purpose Materials annual progress report, October 1, 1979  

SciTech Connect (OSTI)

The scope of Special Purpose Materials covers fusion reactor materials problems other than the first-wall and blanket structural materials, which are under the purview of the ADIP, DAFS, and PMI task groups. Components that are considered as special purpose materials include breeding materials, coolants, neutron multipliers, barriers for tritium control, materials for compression and OH coils and waveguides, graphite and SiC, heat-sink materials, ceramics, and materials for high-field (> 10-T) superconducting magnets. It is recognized that there will be numerous materials problems that will arise during the design and construction of large magnetic-fusion energy devices such as the Engineering Test Facility (ETF) and Demonstration Reactor (DEMO). Most of these problems will be specific to a particular design or project and are the responsibility of the project, not the Materials and Radiation Effects Branch. Consequently, the Task Group on Special Purpose Materials has limited its concern to crucial and generic materials problems that must be resolved if magnetic-fusion devices are to succeed. Important areas specifically excluded include low-field (8-T) superconductors, fuels for hybrids, and materials for inertial-confinement devices. These areas may be added in the future when funding permits.

Not Available

1980-04-01T23:59:59.000Z

71

MATERIALS AND MOLECULAR RESEARCH DIVISION. ANNUAL REPORT 1981  

E-Print Network [OSTI]

of Materials in In-situ Oil Shale Retorting Environments,"of Materials in In-Situ Oil Shale Environments," 8thCorrosion of Metals in Oil Shale Retorting Environments,"

Authors, Various

2010-01-01T23:59:59.000Z

72

MATERIALS AND MOLECULAR RESEARCH DIVISION. ANNUAL REPORT 1981  

E-Print Network [OSTI]

of Materials in In-situ Oil Shale Retorting Environments,"of Materials in In-Situ Oil Shale Environments," 8thUtilization of Metals in Oil Shale Retort Components Alan V.

Authors, Various

2010-01-01T23:59:59.000Z

73

Annual Report of the EURATOM/CCFE Fusion Programme 2012/13 6 Materials  

E-Print Network [OSTI]

Annual Report of the EURATOM/CCFE Fusion Programme 2012/13 6.1 6 Materials 6 Materials 6.1 INTRODUCTION Identifying materials that can maintain their properties for many years while subject to high. For this reason, materials development is receiving increasing attention at CCFE; the more scientific aspects

74

Annual Report of the EURATOM/CCFE Fusion Programme 2013 6 Materials  

E-Print Network [OSTI]

Annual Report of the EURATOM/CCFE Fusion Programme 2013 6.1 6 Materials 6 Materials 6.1 INTRODUCTION A major challenge in fusion research is identifying and testing materials for power plant of neutrons and heat. For this reason, materials development is an important and growing part of CCFE

75

Fusion Materials Semiannual Progress Report for Period Ending December 31, 1998  

SciTech Connect (OSTI)

This is the twenty-fifth in a series of semiannual technical progress reports on fusion materials. This report combines the full spectrum of research and development activities on both metallic and non-metallic materials with primary emphasis on the effects of the neutronic and chemical environment on the properties and performance of materials for in-vessel components. This effort forms one element of the materials program being conducted in support of the Fusion Energy Sciences Program of the U.S. Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately.

Rowcliff, A.F.; Burn, G.

1999-04-01T23:59:59.000Z

76

Summary Report for the Development of Materials for Volatile Radionuclides  

SciTech Connect (OSTI)

The materials development summarized here is in support of the Waste Forms campaign, Volatile Radionuclide task. Specifically, materials are being developed for the removal and immobilization of iodine and krypton, specifically 129I and 85Kr. During FY 2010, aerogel materials were investigated for removal and immobilization of 129I. Two aerogel formulations were investigated, one based on silica aerogels and the second on chalcogenides. For 85Kr, metal organic framework (MOF) structures were investigated.

Strachan, Denis M.; Chun, Jaehun; Henager, Charles H.; Matyas, Josef; Riley, Brian J.; Ryan, Joseph V.; Thallapally, Praveen K.

2010-11-22T23:59:59.000Z

77

Chemistry {ampersand} Materials Science progress report summary of selected research and development topics, FY97  

SciTech Connect (OSTI)

This report contains summaries of research performed in the Chemistry and Materials Science division. Topics include Metals and Ceramics, High Explosives, Organic Synthesis, Instrument Development, and other topics.

Newkirk, L.

1997-12-01T23:59:59.000Z

78

Organic materials for second harmonic generation. Final report  

SciTech Connect (OSTI)

Materials were chosen by screening the Cambridge Crystallographic Index for new noncentrosymmetric crystalline compounds, by screening commercially available materials or by synthesis of unique new substances. Measurements were then made on the powder form of these materials. Langmuir-Blodgett films were deposited and studied. In addition to the above studies, a computer program was developed to calculate (hyper) polarizabilities of organic molecules and thus aid in the selection of materials for testing. The nonlinear molecules have been divided into three classes according to absorption cutoff: 400 to 500 nm, 300 to 400 nm, and 200 to 300 nm. 108 refs., 7 tabs. (WRF)

Twieg, R.J. (comp.)

1985-03-31T23:59:59.000Z

79

MATERIALS AND MOLECULAR RESEARCH DIVISION Annual Report 1977.  

E-Print Network [OSTI]

at room temperature in a hydraulic press. The clamp was thenof such materials. A hydraulic press is used to co~)act

Authors, Various

2011-01-01T23:59:59.000Z

80

MATERIALS AND MOLECULAR RESEARCH DIVISION Annual Report 1977.  

E-Print Network [OSTI]

of Phase Diagrams in Metallurgy and Ceramics, Natl. BureauFillldamental Reactions in Metallurgy, Solid State Physicsthe cell. CXBL 783-7645) of metallurgy and Material Science,

Authors, Various

2011-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "materials clsm reported" 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

MATERIALS AND MOLECULAR RESEARCH DIVISION, ANNUAL REPORT 1976  

E-Print Network [OSTI]

d. Powder Metallurgy Milton R. Pickus, PrincipaZby the Powder Metallurgy Infiltration Method, (M.S. Thesis)I. MATERIALS SCIENCES A. Metallurgy and Ceramics 1. Heavy

Authors, Various

2010-01-01T23:59:59.000Z

82

MATERIALS AND MOLECULAR RESEARCH DIVISION. ANNUAL REPORT 1981  

E-Print Network [OSTI]

Williams Department of Metallurgy and Materials EngineeringEXXON Colloquia in Metallurgy, Linden, NJ, September 4,of Extraction Metallurgy ' 8 1 , London, England, Inst. Min.

Authors, Various

2010-01-01T23:59:59.000Z

83

FY 2008 Progress Report for Lightweighting Materials - 5. Automotive...  

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

and validation of advanced materials and manufacturing technologies to reduce automobile weight without compromising other attributes. 5automotivemetals-steel.pdf More...

84

FY 2008 Progress Report for Lightweighting Materials - 6. Automotive...  

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

and validation of advanced materials and manufacturing technologies to reduce automobile weight without compromising other attributes. 6automotivemetals-crosscutting.pdf...

85

FY 2008 Progress Report for Lightweighting Materials - Cover...  

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

and validation of advanced materials and manufacturing technologies to reduce automobile weight without compromising other attributes. covertptoc.pdf More Documents &...

86

FY 2008 Progress Report for Lightweighting Materials - 8. Polymer...  

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

and validation of advanced materials and manufacturing technologies to reduce automobile weight without compromising other attributes. 8polymercompositesrd.pdf More...

87

FY 2008 Progress Report for Lightweighting Materials - 3. Automotive...  

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

and validation of advanced materials and manufacturing technologies to reduce automobile weight without compromising other attributes. 3automotivemetals-cast.pdf More...

88

Advanced Industrial Materials Program. Annual progress report, FY 1993  

SciTech Connect (OSTI)

Mission of the AIM program is to commercialize new/improved materials and materials processing methods that will improve energy efficiency, productivity, and competitiveness. Program investigators in the DOE national laboratories are working with about 100 companies, including 15 partners in CRDAs. Work is being done on intermetallic alloys, ceramic composites, metal composites, polymers, engineered porous materials, and surface modification. The program supports other efforts in the Office of Industrial Technologies to assist the energy-consuming process industries. The aim of the AIM program is to bring materials from basic research to industrial application to strengthen the competitive position of US industry and save energy.

Stooksbury, F. [comp.

1994-06-01T23:59:59.000Z

89

High Temperature Materials Laboratory User Program: 19th Annual Report, October 1, 2005 - September 30, 2006  

SciTech Connect (OSTI)

Annual Report contains overview of the High Temperature Materials Laboratory User Program and includes selected highlights of user activities for FY2006. Report is submitted to individuals within sponsoring DOE agency and to other interested individuals.

Pasto, Arvid [ORNL

2007-08-01T23:59:59.000Z

90

Fusion reactor materials. Semiannual progress report for period ending September 30, 1993  

SciTech Connect (OSTI)

This is the fifteenth in a series of semiannual technical progress reports on fusion reactor materials. This report combines research and development activities which were previously reported separately in the following progress reports: Alloy Development for Irradiation Performance; Damage Analysis and Fundamental Studies; Special purpose Materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials programs being conducted in support of the Magnetic Fusion Energy Program of the U.S. Department of Energy. The Fusion Reactor Materials Program is a national effort involving several national laboratories, universities, and industries. The purpose of this series of reports is to provide a working technical record for the use of the program participants, and to provide a means of communicating the efforts of materials scientists to the rest of the fusion community, both nationally and worldwide.

Rowcliffe, A.F.; Burn, G.L.; Knee`, S.S.; Dowker, C.L. [comps.

1994-02-01T23:59:59.000Z

91

MATERIALS AND MOLECULAR RESEARCH DIVISION. ANNUAL REPORT 1981  

E-Print Network [OSTI]

and total Immer sion 1n shale oil on the corrosion of steel1013 steel. Exposure to shale oil at 300 C for 100 hoursof Materials in In-situ Oil Shale Retorting Environments,"

Authors, Various

2010-01-01T23:59:59.000Z

92

Material Recovery and Waste Form Development FY 2014 Accomplishments Report  

SciTech Connect (OSTI)

Develop advanced nuclear fuel cycle separation and waste management technologies that improve current fuel cycle performance and enable a sustainable fuel cycle, with minimal processing, waste generation, and potential for material diversion.

Lori Braase

2014-11-01T23:59:59.000Z

93

MATERIALS AND MOLECULAR RESEARCH DIVISION Annual Report 1977.  

E-Print Network [OSTI]

Stainless Steel in Coal Gasification Environments, LBL-733Z.of Materials Used in Coal Gasification Plants, AGA- ERDA-MPCon ~hterials for the Gasification of Coal, presented to the

Authors, Various

2011-01-01T23:59:59.000Z

94

Materials and Chemical Sciences Division annual report, 1987  

SciTech Connect (OSTI)

Research programs from Lawrence Berkeley Laboratory in materials science, chemical science, nuclear science, fossil energy, energy storage, health and environmental sciences, program development funds, and work for others is briefly described. (CBS)

Not Available

1988-07-01T23:59:59.000Z

95

MATERIALS AND MOLECULAR RESEARCH DIVISION. ANNUAL REPORT 1981  

E-Print Network [OSTI]

Immer sion 1n shale oil on the corrosion of steel was alsoof Metals in Oil Shale Environments," NACE Corrosion 82,Levy, "Corrosion of Materials in In-situ Oil Shale Retorting

Authors, Various

2010-01-01T23:59:59.000Z

96

Chemistry and Materials Science progress report, FY 1994. Revision 2  

SciTech Connect (OSTI)

Thrust areas of the weapons-supporting research include surface science, fundamentals of the physics and processing of metals, energetic materials, etc. The laboratory directed R and D include director`s initiatives, individual projects, and transactinium science studies.

NONE

1996-01-01T23:59:59.000Z

97

MATERIALS AND MOLECULAR RESEARCH DIVISION ANNUAL REPORT 1979  

E-Print Network [OSTI]

of Fe-Cr-Ni Alloys in Coal Gasifier Environments," OxidationStructural ~latorials in Coal Gasifier Atmospheres," UCLA,char parti- cles in coal gasifiers consist of materials with

Authors, Various

2013-01-01T23:59:59.000Z

98

3500-hour durability testing of commercial ceramic materials. Interim report  

SciTech Connect (OSTI)

A two-year durability testing program was performed by AiResearch Phoenix to evaluate four commercially available ceramic materials under simulated automotive gas turbine combustor discharge conditions. These conditions included extended cyclic thermal exposures up to 2500/sup 0/F and 3500 h. The four materials selected for evaluation were Norton NCX-34 hot pressed silicon nitride, AiResearch RBN 101 reaction bonded silicon nitride, Carborundum pressureless sintered ..cap alpha..-SiC and British Nuclear Fuels, Ltd. Refel reaction sintered silicon carbide marketed by Pure Carbon Co. These materials initially were exposed to 350 h/1750 cycles at 1200 and 1370/sup 0/C (2200 and 2500/sup 0/F). Subsequent exposures to 1050, 2100, and 3500 h were performed on the materials maintaining 50% of baseline strength after the initial exposure. Additional evaluations of exposed bars included dimension changes, weight changes, dye penetrant, specific damping capacity changes, Scanning Electron Microscope (SEM) fractography and x-ray diffraction.

Carruthers, W.D.; Richerson, D.W.; Benn, K.W.

1980-07-01T23:59:59.000Z

99

Materials Technology Support for Radioisotope Power Systems Final Report  

SciTech Connect (OSTI)

Over the period of this sponsored research, UDRI performed a number of materials related tasks that helped to facilitate increased understanding of the properties and applications of a number of candidate program related materials including; effects of neutron irradiation on tantalum alloys using a 500kW reactor, thermodynamic based modeling of the chemical species in weld pools, and the application of candidate coatings for increased oxidation resistance of FWPF (Fine Weave Pierced Fabric) modules.

Daniel P. Kramer; Chadwick D. Barklay

2008-10-07T23:59:59.000Z

100

Chemistry and Materials Science, 1990--1991. [Second annual report  

SciTech Connect (OSTI)

This 2-year (FY 1990-91) contains 49 technical articles in ten sections: research sampler, metals and alloys, energetic materials, chemistry and physics of advanced materials, bonding and reactions at surfaces and interfaces, superconductivity, energy R and D, waste processing and management, characterization and analysis, and facilities and instrumentation. Two more sections list department personnel, their publications etc., consultants, and summary of department budgets. The articles are processed separately for the data base. (DLC)

Sugihara, T.T.; Bruner, J.M.; McElroy, L.A. [eds.

1991-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "materials clsm reported" 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

MATERIALS AND MOLECULAR RESEARCH DIVISION. ANNUAL REPORT 1978  

E-Print Network [OSTI]

and Reports Powder Metallurgy Milton R. Piokus, Investigatorof a Thermoplastic-Powder Metallurgy Process for the Z. S.Prepared by Powder Metallurgy Techniques . . . . . . . 2.

Authors, Various

2011-01-01T23:59:59.000Z

102

Annual Report of the EURATOM/CCFE Fusion Programme 2011/12 6 Materials  

E-Print Network [OSTI]

Annual Report of the EURATOM/CCFE Fusion Programme 2011/12 6 Materials 6.1 INTRODUCTION Developing materials that can maintain their properties for many years while subject to high fluxes of neutrons and heat in a fusion power plant is one of the biggest challenges in fusion research. Materials will have

103

Manual for Nuclear Materials Management and Safeguards System Reporting and Data Submission  

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

The manual provides detailed instructions for documenting and reporting data submissions for nuclear materials transactions, inventories, and material balances to the Nuclear Materials Management and Safeguards System (NMMSS). Cancels DOE M 474.1-2. Canceled by DOE M 470.4-6.

2003-08-19T23:59:59.000Z

104

Final Report: Laser-Material Interactions Relevant to Analytic Spectroscopy of Wide Band Gap Materials  

SciTech Connect (OSTI)

We summarize our studies aimed at developing an understanding of the underlying physics and chemistry in terms of laser materials interactions relevant to laser-based sampling and chemical analysis of wide bandgap materials. This work focused on the determination of mechanisms for the emission of electrons, ions, atoms, and molecules from laser irradiation of surfaces. We determined the important role of defects on these emissions, the thermal, chemical, and physical interactions responsible for matrix effects and mass-dependent transport/detection. This work supported development of new techniques and technology for the determination of trace elements contained such as nuclear waste materials.

Dickinson, J. T. [Washington State University] [Washington State University

2014-04-05T23:59:59.000Z

105

Conceptual Design Report for the Irradiated Materials Characterization Laboratory (IMCL)  

SciTech Connect (OSTI)

This document describes the design at a conceptual level for the Irradiated Materials Characterization Laboratory (IMCL) to be located at the Materials and Fuels Complex (MFC) at the Idaho National Laboratory (INL). The IMCL is an 11,000-ft2, Hazard Category-2 nuclear facility that is designed for use as a state of the-art nuclear facility for the purpose of hands-on and remote handling, characterization, and examination of irradiated and nonirradiated nuclear material samples. The IMCL will accommodate a series of future, modular, and reconfigurable instrument enclosures or caves. To provide a bounding design basis envelope for the facility-provided space and infrastructure, an instrument enclosure or cave configuration was developed and is described in some detail. However, the future instrument enclosures may be modular, integral with the instrument, or reconfigurable to enable various characterization environments to be configured as changes in demand occur. They are not provided as part of the facility.

Stephanie Austad

2010-06-01T23:59:59.000Z

106

Materials Degradation and Detection (MD2): Deep Dive Final Report  

SciTech Connect (OSTI)

An effort is underway at Pacific Northwest National Laboratory (PNNL) to develop a fundamental and general framework to foster the science and technology needed to support real-time monitoring of early degradation in materials used in the production of nuclear power. The development of such a capability would represent a timely solution to the mounting issues operators face with materials degradation in nuclear power plants. The envisioned framework consists of three primary and interconnected thrust areas including 1) microstructural science, 2) behavior assessment, and 3) monitoring and predictive capabilities. A brief state-of-the-art assessment for each of these core technology areas is discussed in the paper.

McCloy, John S.; Montgomery, Robert O.; Ramuhalli, Pradeep; Meyer, Ryan M.; Hu, Shenyang Y.; Li, Yulan; Henager, Charles H.; Johnson, Bradley R.

2013-02-01T23:59:59.000Z

107

March 2014 Most Viewed Documents for Power Generation And Distribution...  

Office of Scientific and Technical Information (OSTI)

materials (CLSM), reported by ACI Committee 229 Rajendran, N. (1997) 15 > Industrial Power Factor Analysis Guidebook. Electrotek Concepts. (1995) 15 > WABASH RIVER COAL...

108

Materials characterization center workshop on compositional and microstructural analysis of nuclear waste materials. Summary report  

SciTech Connect (OSTI)

The purpose of the Workshop on Compositional and Microstructural Analysis of Nuclear Waste Materials, conducted November 11 and 12, 1980, was to critically examine and evaluate the various methods currently used to study non-radioactive, simulated, nuclear waste-form performance. Workshop participants recognized that most of the Materials Characterization Center (MCC) test data for inclusion in the Nuclear Waste Materials Handbook will result from application of appropriate analytical procedures to waste-package materials or to the products of performance tests. Therefore, the analytical methods must be reliable and of known accuracy and precision, and results must be directly comparable with those from other laboratories and from other nuclear waste materials. The 41 participants representing 18 laboratories in the United States and Canada were organized into three working groups: Analysis of Liquids and Solutions, Quantitative Analysis of Solids, and Phase and Microstructure Analysis. Each group identified the analytical methods favored by their respective laboratories, discussed areas needing attention, listed standards and reference materials currently used, and recommended means of verifying interlaboratory comparability of data. The major conclusions from this workshop are presented.

Daniel, J.L.; Strachan, D.M.; Shade, J.W.; Thomas, M.T.

1981-06-01T23:59:59.000Z

109

MATERIALS AND MOLECULAR RESEARCH DIVISION. ANNUAL REPORT 1981  

E-Print Network [OSTI]

Bonfiglio Bryndza Carriere Comita Janowicz Seidler SeidlerIBL Reports 1. P. B. Comita, M. R. Berman, C. B. Moore and5. T. P. Lockhart, P. B. Comita and R. G. Bergman," Kinetic

Authors, Various

2010-01-01T23:59:59.000Z

110

MATERIALS AND MOLECULAR RESEARCH DIVISION. ANNUAL REPORT 1980  

E-Print Network [OSTI]

Office of Conservation and Solar Energy, U.S. Department ofOffice of Conservation and Solar Energy, DOE, arc reportedSecretary for Conservation and Solar Energy, Office of

Searcy, Alan W.

2010-01-01T23:59:59.000Z

111

MATERIALS AND MOLECULAR RESEARCH DIVISION ANNUAL REPORT 1979  

E-Print Network [OSTI]

Publications and Reports d. Oil Shale Retort Components A.in Simulated In-Situ Oil Shale Retorts Research Plans forP. 1111ittle and A. V. Levy, "Oil Shale Eetort Components,"

Authors, Various

2013-01-01T23:59:59.000Z

112

University of Illinois at Urbana-Champaign, Materials Research Laboratory progress report for FY 1991  

SciTech Connect (OSTI)

The Materials Research Laboratory at the University of Illinois is an interdisciplinary laboratory operated in the College of Engineering. Its focus is the science of materials and it supports research in the areas of condensed matter physics, solid state chemistry, and materials science. This report addresses topics such as: an MRL overview; budget; general programmatic and institutional issues; new programs; research summaries for metallurgy, ceramics, solid state physics, and materials chemistry.

Not Available

1991-10-01T23:59:59.000Z

113

Chemistry and Materials Science. Progress report, first half, FY 1993  

SciTech Connect (OSTI)

Thrust areas of the weapons-supporting research are growth, structure, and reactivity of surfaces and thin films; uranium research; physics and processing of metals; energetic materials; etc. The laboratory-directed R and D include director`s initiatives and individual projects, and transactinium institute studies.

Not Available

1993-07-01T23:59:59.000Z

114

Advanced Industrial Materials (AIM) Program annual progress report, FY 1997  

SciTech Connect (OSTI)

The Advanced Industrial Materials (AIM) Program is a part of the Office of Industrial Technologies (OIT), Energy Efficiency and Renewable Energy, US Department of Energy (DOE). The mission of AIM is to support development and commercialization of new or improved materials to improve energy efficiency, productivity, product quality, and reduced waste in the major process industries. OIT has embarked on a fundamentally new way of working with industries--the Industries of the Future (IOF) strategy--concentrating on the major process industries that consume about 90% of the energy and generate about 90% of the waste in the industrial sector. These are the aluminum, chemical, forest products, glass, metalcasting, and steel industries. OIT has encouraged and assisted these industries in developing visions of what they will be like 20 or 30 years into the future, defining the drivers, technology needs, and barriers to realization of their visions. These visions provide a framework for development of technology roadmaps and implementation plans, some of which have been completed. The AIM Program supports IOF by conducting research and development on materials to solve problems identified in the roadmaps. This is done by National Laboratory/industry/university teams with the facilities and expertise needed to develop new and improved materials. Each project in the AIM Program has active industrial participation and support.

NONE

1998-05-01T23:59:59.000Z

115

Materials support for HITAF. Final report for Phase 1  

SciTech Connect (OSTI)

Improvements in coal-fired systems will require a change from steam turbines to gas turbines using air as working fluid; pressurized ceramic heat exchangers operating up to 1600 C will be needed. Leading candidate materials are SiC-based ceramics. Mechanical properties of 3 materials are compared in this work: NT230 Si/SiC from Saint Gobain Norton, {beta}-SiC from Coors Ceramics Co., and Lanxide DIMOX SiCp/Al{sub 2}O{sub 3} from Du Pont Lanxide Composites Inc. The first material is siliconized Si carbide, the second is sintered. They all were tested in 4-point flexure at RT and 1100 and 1400 C. Fast-fracture tests were carried out. Slow crack growth was investigated. Failure modes were studied using optical microscopy and SEM. Four materials were exposed to two coal ashes at two different temperatures. In the comparison, Coors {beta}-SiC stands out from a strength and reliability standpoint when exposed to air at high temperatures. Lanxide DIMOX withstood coal ash exposure well.

Breder, K.; Tennery, V.J.

1995-03-01T23:59:59.000Z

116

Materials compatibility with the volcanic environment. Final report  

SciTech Connect (OSTI)

Attempts were made to run materials compatibility, volcanic gas collection, and heat transfer experiments during the 1977 Kilauea eruption. Preliminary results from the recovered samples showed that Fe, Ni, and Fe-Ni alloys were the most heavily oxidized. The Mo and W alloys showed some attack and only neglible reaction was seen on 310 stainless, Hastelloy C, Inconel 600, Inconel 718, Rene 41, and Nichrome. Results are qualitative only. (DLC)

Htun, K.M.

1984-03-08T23:59:59.000Z

117

Fusion materials semiannual progress report for the period ending March 31, 1995  

SciTech Connect (OSTI)

This is the eighteenth in a series of semiannual technical progress reports on fusion materials. This report combines research and development activities which were previously reported separately in the following progress reports: {sm_bullet} Alloy Development for Irradiation Performance. {sm_bullet} Damage Analysis and Fundamental Studies. {sm_bullet} Special Purpose Materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials programs being conducted in support of the Magnetic Fusion Energy Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. The Fusion Materials Program is a national effort involving several national laboratories, universities, and industries. The purpose of this series of reports is to provide a working technical record for the use of the program participants, and to provide a means of communicating the efforts of materials scientists to the rest of the fusion community, both nationally and worldwide. This report has been compiled and edited under the guidance of A.F. Rowcliffe by Gabrielle Burn, Oak Ridge National Laboratory. Their efforts, and the efforts of the many persons who made technical contributions, are gratefully acknowledged.

NONE

1995-07-01T23:59:59.000Z

118

Center for Materials Science, Los Alamos National Laboratory. Status report, October 1, 1990--September 30, 1991  

SciTech Connect (OSTI)

This report summarizes the progress of the Center for Materials Science (CMS) from October 1, 1990 to September 30, 1991, and is the nineth such annual report. It has been a year of remarkable progress in building the programs of the Center. The extent of this progress is described in detail. The CMS was established to enhance the contribution of materials science and technology to the Laboratory`s defense, energy and scientific missions, and the Laboratory. In carrying out these responsibilities it has accepted four demanding missions: (1) Build a core group of highly rated, established materials scientists and solid state physicists. (2) Promote and support top quality, interdisciplinary materials research programs at Los Alamos. (3) Strengthen the interactions of materials science and Los Alamos with the external materials science community. and (4) Establish and maintain modern materials research facilities in a readily accessible, central location.

Parkin, D.M.; Boring, A.M. [comps.

1991-10-01T23:59:59.000Z

119

Engineered Materials for Cesium and Strontium Storage Final Technical Report  

SciTech Connect (OSTI)

Closing the nuclear fuel cycle requires reprocessing spent fuel to recover the long-lived components that still have useful energy content while immobilizing the remnant waste fission products in stable forms. At the genesis of this project, next generation spent fuel reprocessing methods were being developed as part of the U.S. Department of Energy's Advanced Fuel Cycle Initiative. One of these processes was focused on solvent extraction schemes to isolate cesium (Cs) and strontium (Sr) from spent nuclear fuel. Isolating these isotopes for short-term decay storage eases the design requirements for long-term repository disposal; a significant amount of the radiation and decay heat in fission product waste comes from Cs-137 and Sr-90. For the purposes of this project, the Fission Product Extraction (FPEX) process is being considered to be the baseline extraction method. The objective of this project was to evaluate the nature and behavior of candidate materials for cesium and strontium immobilization; this will include assessments with minor additions of yttrium, barium, and rubidium in these materials. More specifically, the proposed research achieved the following objectives (as stated in the original proposal): (1) Synthesize simulated storage ceramics for Cs and Sr using an existing labscale steam reformer at Purdue University. The simulated storage materials will include aluminosilicates, zirconates and other stable ceramics with the potential for high Cs and Sr loading. (2) Characterize the immobilization performance, phase structure, thermal properties and stability of the simulated storage ceramics. The ceramic products will be stable oxide powders and will be characterized to quantify their leach resistance, phase structure, and thermophysical properties. The research progressed in two stages. First, a steam reforming process was used to generate candidate Cs/Sr storage materials for characterization. This portion of the research was carried out at Purdue University and is detailed in Appendix A. Steam reforming proved to be too rigorous for efficient The second stage of this project was carried out at Texas A&M University and is Detailed in Appendix B. In this stage, a gentler ceramic synthesis process using Cs and Sr loaded kaolinite and bentonite clays was developed in collaboration with Dr. M. Kaminski at Argonne National Laboratory.

Sean M. McDeavitt

2010-04-14T23:59:59.000Z

120

Hazardous material minimization for radar assembly. Final report  

SciTech Connect (OSTI)

The Clean Air Act Amendment, enacted in November 1990, empowered the Environmental Protection Agency (EPA) to completely eliminate the production and usage of chlorofluorocarbons (CFCs) by January 2000. A reduction schedule for methyl chloroform beginning in 1993 with complete elimination by January 2002 was also mandated. In order to meet the mandates, the processes, equipment, and materials used to solder and clean electronic assemblies were investigated. A vapor-containing cleaning system was developed. The system can be used with trichloroethylene or d-Limonene. The solvent can be collected for recycling if desired. Fluxless and no-clean soldering were investigated, and the variables for a laser soldering process were identified.

Biggs, P.M.

1997-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "materials clsm reported" 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

Fusion Reactor Materials semiannual progress report for the period ending March 31, 1992  

SciTech Connect (OSTI)

This is the twelfth in a series of semiannual technical progress reports on fusion reactor materials. This report combines research and development activities which were previously reported separately in the following progress reports: Alloy Development for Irradiation Performance; Damage Analysis and Fundamental Studies; and Special Purpose Materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials programs being conducted in support of the Magnetic Fusion Energy Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. The Fusion Reactor Materials Program is a national effort involving several national laboratories, universities, and industries. The purpose of this series of reports is to provide a working technical record for the use of the program participants, and to provide a means of communicating the efforts of materials scientists to the rest of the fusion community, both nationally and worldwide.

Not Available

1992-07-01T23:59:59.000Z

122

Fusion reactor materials semiannual progress report for period ending September 30, 1990  

SciTech Connect (OSTI)

This is the ninth in series of semiannual technical progress reports on fusion reactor materials. This report combines research and development activities which were previously reported separately in the following technical progress reports: Alloy Development of Irradiation Performance; Damage Analysis and Fundamental Studies; and Special Purpose Materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials program being conducted in support of the Magnetic Fusion Energy Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. The Fusion Reactor Materials Program is a national effort involving several national laboratories, universities, and industries. The purpose of this series of reports is to provide a working technical record for the use of the program participants, and to provide a means of communicating the efforts of materials scientists to the rest of the fusion community, both nationally and worldwide.

Not Available

1991-04-01T23:59:59.000Z

123

2014 Annual Merit review Results Report - Materials Technologies |  

Energy Savers [EERE]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustionImprovement3 Beryllium-Associated Worker RegistryDepartment of Energy review Results Report

124

Development of chemical vapor composites, CVC materials. Final report  

SciTech Connect (OSTI)

Industry has a critical need for high-temperature operable ceramic composites that are strong, non-brittle, light weight, and corrosion resistant. Improvements in energy efficiency, reduced emissions and increased productivity can be achieved in many industrial processes with ceramic composites if the reaction temperature and pressure are increased. Ceramic composites offer the potential to meet these material requirements in a variety of industrial applications. However, their use is often restricted by high cost. The Chemical Vapor composite, CVC, process can reduce the high costs and multiple fabrication steps presently required for ceramic fabrication. CVC deposition has the potential to eliminate many difficult processing problems and greatly increase fabrication rates for composites. With CVC, the manufacturing process can control the composites` density, microstructure and composition during growth. The CVC process: can grow or deposit material 100 times faster than conventional techniques; does not require an expensive woven preform to infiltrate; can use high modulus fibers that cannot be woven into a preform; can deposit composites to tolerances of less than 0.025 mm on one surface without further machining.

NONE

1998-10-05T23:59:59.000Z

125

Energy Materials Coordinating Committee (EMaCC) Fiscal Year 1999 annual technical report  

SciTech Connect (OSTI)

The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department`s materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. This report summarizes EMaCC activities for FY 1999 and describes the materials research programs of various offices and divisions within the Department.

None

2000-10-31T23:59:59.000Z

126

Surface-Gasification Materials Program. Semiannual progress report for the period ending March 31, 1983  

SciTech Connect (OSTI)

Contents of this semiannual report include the following: introduction; (1) plant materials surveillance tests (Illinois Institute of Technology); (2) slagging gasifier refractories - appliction/evaluation (Argonne National Laboratory); (3) protective clothing and claddings - application/evaluation (ANL); (4) ceramic application technology - brittle material design (LANL); (5) advanced pressure vessel materials technology (ORNL); (6) electroslag component casting (ORNL); (7) cost reduction of the electroslag casting manufacturing process (CMU); (8) materials review and component failure analysis in support of coal gasification processes and plants (ANL); (9) process plant materials review, evaluation, and support (ORNL).

Bradley, R.A. (comp.)

1983-05-01T23:59:59.000Z

127

Energy Materials Coordinating Committee (EMaCC): Fiscal year 1996. Annual technical report  

SciTech Connect (OSTI)

The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department`s materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. The EMaCC reports to the Director of the Office of Energy Research in his or her capacity as overseer of the technical programs of the Department. This annual technical report is mandated by the EMaCC terms of reference. This report summarizes EMaCC activities for FY 1996 and describes the materials research programs of various offices and divisions within the Department.

NONE

1997-08-01T23:59:59.000Z

128

Purchasing and Materials Management Organization, Sandia National Laboratories annual report, fiscal year 1993  

SciTech Connect (OSTI)

This report summarizes the purchasing and transportation activities of the Purchasing and Materials Management Organization for Fiscal Year 1993. Activities for both the New Mexico and California locations are included.

Martin, D.R.

1994-02-01T23:59:59.000Z

129

Building Thermal Envelope Systems and Materials (BTESM) progress report for DOE Office of Buildings Energy Research  

SciTech Connect (OSTI)

The Monthly Report of the Building Thermal Envelope Systems and Materials (BTESM) Program is a monthly update of both in-house ORNL projects and subcontract activities in the research areas of building materials, wall systems, foundations, roofs, building diagnostics, and research utilization and technology transfer. Presentations are not stand-alone paragraphs every month. Their principal values are the short-time lapse between accomplishment and reporting and their evolution over a period of several months.

Burn, G. (comp.)

1990-01-01T23:59:59.000Z

130

Materials Corrosion and Mitigation Strategies for APT: End of Year Report, FY '96  

E-Print Network [OSTI]

Materials Corrosion and Mitigation Strategies for APT: End of Year Report, FY '96 R. Scott Lillard, Darryl P. Butt Materials Corrosion and Environmental Effects Laboratory MST-6, Metallurgy Los Alamos accomplishment in FY '96 was the design and fabrication of the corrosion probes to be used "In Beam" during

131

Materials Corrosion and Mitigation Strategies for APT, End of FY '97 Report  

E-Print Network [OSTI]

Materials Corrosion and Mitigation Strategies for APT, End of FY '97 Report: I. Inconel 718 In-Beam Corrosion Rates from the '97 A6 Irradiation R. Scott Lillard, Donald L. Pile, Darryl P. Butt Materials Corrosion & Environmental Effects Lab MST-6, Metallurgy Group Los Alamos National Laboratory, Los Alamos NM

132

Materials Corrosion and Mitigation Strategies for APT, End of FY '97 Report  

E-Print Network [OSTI]

Materials Corrosion and Mitigation Strategies for APT, End of FY '97 Report: II. Out-of-Beam Corrosion Rates and Water Analysis from the '97 A6 Irradiation R. Scott Lillard, Donald L. Pile, Darryl P. Butt Materials Corrosion & Environmental Effects Lab MST-6, Metallurgy Group Los Alamos National

133

Performance testing of elastomeric seal materials under low and high temperature conditions: Final report  

SciTech Connect (OSTI)

The US Department of Energy Offices of Defense Programs and Civilian Radioactive Waste Management jointly sponsored a program to evaluate elastomeric O-ring seal materials for radioactive material shipping containers. The report presents the results of low- and high-temperature tests conducted on 27 common elastomeric compounds.

BRONOWSKI,DAVID R.

2000-06-01T23:59:59.000Z

134

Materials research and beam line operation utilizing NSLS. Progress report  

SciTech Connect (OSTI)

MATRIX, a participating research team of Midwest x-ray scattering specialists, continues to operate beam line X-18A at NSLS. Operations of this line now provides state-of-the-art capabilities to a wide range of people in the Materials Science and Engineering research community. Improvements of the beam line continue to be a focus of MATRIX. Throughout this past year the emphasis has been shifting towards improvement in ``user friendly`` aspects. Simplified control operations and a shift to single-user personal computer has been a major part of the effort. Over the past year the full 242 operational days were utilized. Beam line test and evaluation consumed 21 days with eight MATRIX groups combining to use 170 days. General user demand for use of the beam line continues to be strong and three groups were provided 51 operating days. Research production has been growing as NSLS and the beam line become a more stable type of operation. For 1990 the MATRIX group published nine articles. To data for 1991 the same group has published, submitted, or has in preparation twelve articles. Among the milestones achieved last year on MATRIX member obtained the first data from a new ultra high vacuum chamber with low temperature capability. This is a unique capability at NSLS. Another member demonstrated grazing incidence small angle x-ray scattering capability for kinetic studies of film growth.

Liedl, G.L.

1991-10-01T23:59:59.000Z

135

Materials research and beam line operation utilizing NSLS. Progress report  

SciTech Connect (OSTI)

MATRIX, a participating research team of Midwest x-ray scattering specialists, continues to operate beam line X-18A at NSLS. Operations of this line now provides state-of-the-art capabilities to a wide range of people in the Materials Science and Engineering research community. Improvements of the beam line continue to be a focus of MATRIX. Throughout this past year the emphasis has been shifting towards improvement in ``user friendly`` aspects. Simplified control operations and a shift to single-user personal computer has been a major part of the effort. Over the past year all 232 operational days were fully utilized. Beam line tests coupled with MATRIX members combined to use 284 days. General user demand for use of the beam line continues to be strong and four groups were provided 48 operating days. Research production has been growing as NSLS and the beam line become a more stable type of operation. For 1992 the MATRIX group published six articles. To date, for 1993 the same group has published, submitted, or has in preparation nine articles. Recent research milestones include: the first quantitative structural information on the as-quenched and early stages of decomposition of supersaturated Al-Li alloys; the first quantitative diffuse scattering measurements on a complex system (Co substitute for Cu YBCO superconductor); demonstration of capabilities of a new UHV surface diffraction chamber with in-situ characterization and temperature control (30-1300K); feasibility of phasing structure factors in a quasicrystal using multiple Bragg scattering.

Liedl, G.L.

1993-06-01T23:59:59.000Z

136

Nuclear materials stabilization and packaging. Quarterly progress report, October 1--December 31, 1995  

SciTech Connect (OSTI)

Progress is reported for Los Alamos Nuclear Materials Stabilization and Packaging projects for the first quarter of Fiscal Year 1996. Development and production activities in Plutonium Recovery and Processing, Plutonium Packaging, and Uranium Recovery and Processing are covered. Packaging quality assurance activities are reported.

Chidester, K.M. [comp.

1996-05-01T23:59:59.000Z

137

Physical test report for drop test of a 9974 radioactive material shipping packaging  

SciTech Connect (OSTI)

This report presents the drop test results for the 9974 radioactive material shipping package being dropped onto 6-inch diameter, 40-inch long puncture pin. Also reported are the drop test resuls for a 30-foot impact that failed the drum confinement boundary. The purpose of these drops was to show that the package lid would remain attached to the drum.

Blanton, P.S. [Westinghouse Savannah River Company, AIKEN, SC (United States)

1997-10-01T23:59:59.000Z

138

Test and evaluation of computerized nuclear material accounting methods. Final report  

SciTech Connect (OSTI)

In accordance with the definition of a Material Balance Area (MBA) as a well-defined geographical area involving an Integral operation, the building housing the BFS-1 and BFS-1 critical facilities is considered to consist of one MBA. The BFS materials are in the form of small disks clad in stainless steel and each disk with nuclear material has its own serial number. Fissile material disks in the BFS MBA can be located at three key monitoring points: BFS-1 facility, BFS-2 facility and main storage of BFS fissile materials (storage 1). When used in the BFS-1 or BFS-2 critical facilities, the fissile material disks are loaded in tubes (fuel rods) forming critical assembly cores. The following specific features of the BFS MBA should be taken into account for the purpose of computerized accounting of nuclear material: (1) very large number of nuclear material items (about 70,000 fissile material items); and (2) periodically very intensive shuffling of nuclear material items. Requirements for the computerized system are determined by basic objectives of nuclear material accounting: (1) providing accurate information on the identity and location of all items in the BFS material balance area; (2) providing accurate information on location and identity of tamper-indicating devices; (3) tracking nuclear material inventories; (4) issuing periodic reports; (5) assisting with the detection of material gains or losses; (6) providing a history of nuclear material transactions; (7) preventing unauthorized access to the system and data falsification. In August 1995, the prototype computerized accounting system was installed on the BFS facility for trial operation. Information on two nuclear material types was entered into the data base: weapon-grade plutonium metal and 36% enriched uranium dioxide. The total number of the weapon-grade plutonium disks is 12,690 and the total number of the uranium dioxide disks is 1,700.

NONE

1995-12-31T23:59:59.000Z

139

Radioactive materials released from nuclear power plants: Annual report, 1993. Volume 14  

SciTech Connect (OSTI)

Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1993 have been compiled and reported. The summary data for the years 1974 through 1992 are included for comparison. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1993 release data are summarized in tabular form. Data covering specific radionuclides are summarized.

Tichler, J.; Doty, K.; Lucadamo, K. [Brookhaven National Lab., Upton, NY (United States)

1995-12-01T23:59:59.000Z

140

Surface-gasification materials program. Semiannual progress report for the period ending March 31, 1982  

SciTech Connect (OSTI)

The objective of the Surface Gasification Materials Program is to conduct research and development on materials for application to the specific needs of coal gasification systems. The Program is divided into two subprograms: (1) the Gasification Systems Fabrication Technology Program and (2) the Materials Application and Development Program. The purpose of the Gasification Systems Fabrication Technology Program is to evaluate innovative fabrication methods which have the potential to lower costs and improve reliability and safety for gasifier vessels and components. The purpose of the Materials Application and Development Program is to conduct engineering-scale development and application of materials for coal gasification systems to ensure that the materials of construction for pilot plants and future large-scale plants can be properly selected and specified. The management of materials projects in support of surface gasification sponsored by the Headquarters DOE Gasification Division has been defined in an April 16, 1982 METC-sponsored agreement transmitted to DOE field offices and performing contractors. This agreement recognizes the lead role in fossil energy materials delegated by METC to the DOE Oak Ridge Operations Office and the Oak Ridge National Laboratory. The ORNL Fossil Energy Materials Program Office compiles and issues this combined semiannual progress report from camera-ready copies submitted by each of the participating organizations. Distribution is as shown on pages 59 to 63. Future reports will be issued on a semiannual basis to a similar distribution.

Not Available

1982-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "materials clsm reported" 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

Energy Materials Coordinating Committee (EMaCC): Annual technical report, fiscal year 1993  

SciTech Connect (OSTI)

The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department`s materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. This report summarizes EMaCC activities for FY 1993 and describes the materials research programs of various offices and divisions within the Department. The program descriptions consist of a funding summary for each Assistant Secretary office and the Office of Energy Research, and detailed project summaries with project goals and accomplishments. The FY 1993 budget summary table for DOE Materials Activities in each of the programs is presented.

Not Available

1994-07-01T23:59:59.000Z

142

Surface Gasification Materials Program. Semiannual progress report for the period ending September 30, 1982  

SciTech Connect (OSTI)

The objective of the Surface Gasification Materials Program is to conduct research and development on materials for application to the specific needs of coal gasification systems. The Program is divided into two subprograms: (1) the Gasification Systems Fabrication Technology Program and (2) the Materials Application and Development Program. The purpose of the Gasification Systems Fabrication Technology Program is to evaluate innovative fabrication methods which have the potential to lower costs and improve reliability and safety for gasifier vessels and components. The purpose of the Materials Application and Development Program is to conduct engineering-scale development and application of materials for coal gasification systems to ensure that the materials of construction for pilot plants and future large-scale plants can be properly selected and specified. The Morgantown Energy Technology Center (METC), in its lead role for gasification projects, is responsible for ensuring that the Surface Gasification Materials Program is responsive to the needs for gasification systems. Under its lead role for fossil energy materials, the Oak Ridge Operations Office (ORO), is responsible for the planning, implementation, and management of the program in accordance with guidance received from METC. The ORNL Fossil Energy Materials Program Office compiles and issues this combined semiannual progress report from camera-ready copies submitted by each of the participating organizations.

Not Available

1982-12-01T23:59:59.000Z

143

Annual report on strategic special nuclear material inventory differences, April 1, 1990--March 31, 1991  

SciTech Connect (OSTI)

This report of unclassified Inventory Difference (ID's) covers the twelve months from April 1, 1990 through March 31, 1991 for all key Department of Energy (DOE) and DOE contractor operated facilities possessing strategic special nuclear materials. Classified information is not included in this report. This classified information includes data for the Rocky Flats and Y-12 nuclear weapons production facilities or facilities under ID investigation. However, classified ID data from such facilities receive the same scrutiny and analyses as the included data.

Not Available

1992-01-01T23:59:59.000Z

144

UBC Social Ecological Economic Development Studies (SEEDS) Student Report An Investigation into the Red Listed Material: Pressure Treated Wood  

E-Print Network [OSTI]

into the Red Listed Material: Pressure Treated Wood (Preservative Infused) and Possible Alternatives Abby Yuen of a project/report". #12;APSC 261 An Investigation into the Red Listed Material: Pressure Treated Wood. Pressure treated wood, a commonly used building material in British Columbia, is a red-listed material

145

Publications Forest Research publishes a wide range of material, from corporate reports and plans, to  

E-Print Network [OSTI]

Holt Research Forest by Andy J. Moffat (free) The quest for sustainable energy: woodfuel meetsPublications Forest Research publishes a wide range of material, from corporate reports and plans-reviewed articles in scientific journals and produce books through external publishing houses. 50 Forest Research

146

Final LDRD report : advanced materials for next generation high-efficiency thermochemistry.  

SciTech Connect (OSTI)

Despite rapid progress, solar thermochemistry remains high risk; improvements in both active materials and reactor systems are needed. This claim is supported by studies conducted both prior to and as part of this project. Materials offer a particular large opportunity space as, until recently, very little effort apart from basic thermodynamic analysis was extended towards understanding this most fundamental component of a metal oxide thermochemical cycle. Without this knowledge, system design was hampered, but more importantly, advances in these crucial materials were rare and resulted more from intuition rather than detailed insight. As a result, only two basic families of potentially viable solid materials have been widely considered, each of which has significant challenges. Recent efforts towards applying an increased level of scientific rigor to the study of thermochemical materials have provided a much needed framework and insights toward developing the next generation of highly improved thermochemically active materials. The primary goal of this project was to apply this hard-won knowledge to rapidly advance the field of thermochemistry to produce a material within 2 years that is capable of yielding CO from CO2 at a 12.5 % reactor efficiency. Three principal approaches spanning a range of risk and potential rewards were pursued: modification of known materials, structuring known materials, and identifying/developing new materials for the application. A newly developed best-of-class material produces more fuel (9x more H2, 6x more CO) under milder conditions than the previous state of the art. Analyses of thermochemical reactor and system efficiencies and economics were performed and a new hybrid concept was reported. The larger case for solar fuels was also further refined and documented.

Ambrosini, Andrea; Miller, James Edward; Allendorf, Mark D. [Sandia National Laboratories, Livermore, CA] [Sandia National Laboratories, Livermore, CA; Coker, Eric Nicholas; Ermanoski, Ivan; Hogan, Roy E.,; McDaniel, Anthony H. [Sandia National Laboratories, Livermore, CA] [Sandia National Laboratories, Livermore, CA

2014-01-01T23:59:59.000Z

147

CONTRACTOR HAZARDOUS MATERIALS INVENTORY REPORT Project Name: ORNL Y-12 Project Begin Date: Estimated Project End Date  

E-Print Network [OSTI]

CONTRACTOR HAZARDOUS MATERIALS INVENTORY REPORT Project Name: ORNL Y-12 Project Begin Date: Phone Numbers: Project Manager: Field Representative: SHEST Representative: List of Hazardous Materials: Estimated Project End Date: Contractor/Service Subcontractor Name: Contractor/Service Subcontractor Address

Pennycook, Steve

148

A rheometer for measuring the material moduli for granular solids. Quarterly progress report, March 1, 1993--May 31, 1993  

SciTech Connect (OSTI)

This report describes the design of an orthogonal rheometer for the measuring of properties of granular materials such as coal. A section is presented on constitutive modeling of granular materials based on continuum theory.

Rajagopal, K.R.

1996-02-01T23:59:59.000Z

149

Material report in support to RCC-MRX code 2010 stainless steel parts and products  

SciTech Connect (OSTI)

This paper presents the Material Report dedicated to stainless steels parts and products issued by AFCEN (Association Francaise pour les regles de Conception et de Construction des Materiels des Chaudieres Electro-Nucleaires) in support to RCC-MRx 2010 Code. The RCC-MRx Code is the result of the merger of the RCC-MX 2008, developed in the context of the research reactor Jules Horowitz Reactor project, in the RCC-MR 2007, which set up rules applicable to the design of components operating at high temperature and to the Vacuum Vessel of ITER (a presentation of RCC-MRx 2010 Code is the subject of another paper proposed in this Congress; it explains in particular the status of this Code). This Material Report is part of a set of Criteria of RCC-MRx (this set of Criteria is under construction). The Criteria aim at explaining the design and construction rules of the Code. They cover analyses rules as well as part procurement, welding, methods of tests and examination and fabrication rules. The Material Report particularly provides justifications and explanations on requirements and features dealing with parts and products proposed in the Code. The Material Report contains the following information: Introduction of the grade(s): codes and standards and Reference Procurement Specifications covering parts and products, applications and experience gained, - Physical properties, - Mechanical properties used for design calculations (base metal and welds): basic mechanical properties, creep mechanical properties, irradiated mechanical properties, - Fabrication: experience gained, metallurgy, - Welding: weldability, experience gained during welding and repair procedure qualifications, - Non-destructive examination, - In-service behaviour. In the article, examples of data supplied in the Material Report dedicated to stainless steels will be exposed. (authors)

Ancelet, Olivier; Lebarbe, Thierry [CEA Saclay, DEN-DANS-DM2S, Gif-sur-Yvette, (France); Dubiez-Le Goff, Sophie; Bonne, Dominique; Gelineau, Odile [Areva NP, Lyon, (France)

2012-07-01T23:59:59.000Z

150

TITLE III EVALUATION REPORT FOR THE MATERIAL AND PERSONNEL HANDLING SYSTEM  

SciTech Connect (OSTI)

This Title III Evaluation Report (TER) provides the results of an evaluation that was conducted on the Material and Personnel Handling System. This TER has been written in accordance with the ''Technical Document Preparation Plan for the Mined Geologic Disposal System Title III Evaluation Reports'' (BA0000000-01717-4600-00005 REV 03). The objective of this evaluation is to provide recommendations to ensure consistency between the technical baseline requirements, baseline design, and the as-constructed Material and Personnel Handling System. Recommendations for resolving discrepancies between the as-constructed system, the technical baseline requirements, and the baseline design are included in this report. Cost and Schedule estimates are provided for all recommended modifications.

T. A. Misiak

1998-05-21T23:59:59.000Z

151

Audit Report on "The Department's Management of Nuclear Materials Provided to Domestic Licensees"  

SciTech Connect (OSTI)

The objective if to determine whether the Department of Energy (Department) was adequately managing its nuclear materials provided to domestic licensees. The audit was performed from February 2007 to September 2008 at Department Headquarters in Washington, DC, and Germantown, MD; the Oak Ridge Office and the Oak Ridge National Laboratory in Oak Ridge, TN. In addition, we visited or obtained data from 40 different non-Departmental facilities in various states. To accomplish the audit objective, we: (1) Reviewed Departmental and Nuclear Regulatory Commission (NRC) requirements for the control and accountability of nuclear materials; (2) Analyzed a Nuclear Materials Management and Safeguards System (NMMSS) report with ending inventory balances for Department-owned nuclear materials dated September 30, 2007, to determine the amount and types of nuclear materials located at non-Department domestic facilities; (3) Held discussions with Department and NRC personnel that used NMMSS information to determine their roles and responsibilities related to the control and accountability over nuclear materials; (4) Selected a judgmental sample of 40 non-Department domestic facilities; (5) Met with licensee officials and sent confirmations to determine whether their actual inventories of Department-owned nuclear materials were consistent with inventories reported in the NMMSS; and, (6) Analyzed historical information related to the 2004 NMMSS inventory rebaselining initiative to determine the quantity of Department-owned nuclear materials that were written off from the domestic licensees inventory balances. This performance audit was conducted in accordance with generally accepted Government auditing standards. Those standards require that we plan and perform the audit to obtain sufficient, appropriate evidence to provide a reasonable basis for our findings and conclusions based on our audit objective. We believe that the evidence obtained provides a reasonable basis for our findings and conclusions based on our audit objectives. The audit included tests of controls and compliance with laws and regulations related to managing the Department-owned nuclear materials provided to non-Departmental domestic licensees. Because our review was limited it would not necessarily have disclosed all internal control deficiencies that may have existed at the time of our audit. We examined the establishment of performance measures in accordance with Government Performance and Results Act of 1993, as they related to the audit objective. We found that the Department had established performance measures related to removing or disposing of nuclear materials and radiological sources around the world. We utilized computer generated data during our audit and performed procedures to validate the reliability of the information as necessary to satisfy our audit objective. As noted in the report, we questioned the reliability of the NMMSS data.

None

2009-02-01T23:59:59.000Z

152

High performance materials in coal conversion utilization. Technical progress report, October 1, 1994--December 31, 1994  

SciTech Connect (OSTI)

This is the fifth quarterly report on a three year grant regarding {open_quotes}High Performance Materials in Coal Conversion Utilization.{close_quotes} The grant is for a joint university/industry effort under the US Department of Energy (DOE) University Coal Research Program. The University of Tennessee Space Institute (UTSI) is the prime contractor and The University of Pennsylvania and Lanxide Corporation are subcontractors. UTSI has completed the planned laboratory exposure tests involving pulverized coal slag on the production Lanxide DIMOX{trademark} ceramic composite material. In addition, the strength testing (at temperature) of C-ring sections of the production composite is complete.

NONE

1995-01-01T23:59:59.000Z

153

Process Knowledge Summary Report for Materials and Fuels Complex Contact-Handled Transuranic Debris Waste  

SciTech Connect (OSTI)

This Process Knowledge Summary Report summarizes the information collected to satisfy the transportation and waste acceptance requirements for the transfer of transuranic (TRU) waste between the Materials and Fuels Complex (MFC) and the Advanced Mixed Waste Treatment Project (AMWTP). The information collected includes documentation that addresses the requirements for AMWTP and the applicable portion of their Resource Conservation and Recovery Act permits for receipt and treatment of TRU debris waste in AMWTP. This report has been prepared for contact-handled TRU debris waste generated by the Idaho National Laboratory at MFC. The TRU debris waste will be shipped to AMWTP for purposes of supercompaction. This Process Knowledge Summary Report includes information regarding, but not limited to, the generation process, the physical form, radiological characteristics, and chemical contaminants of the TRU debris waste, prohibited items, and packaging configuration. This report, along with the referenced supporting documents, will create a defensible and auditable record for waste originating from MFC.

R. P. Grant; P. J. Crane; S. Butler; M. A. Henry

2010-02-01T23:59:59.000Z

154

Annual report on strategic special nuclear material inventory differences, April 1, 1990--March 31, 1991  

SciTech Connect (OSTI)

This report of unclassified Inventory Difference (ID`s) covers the twelve months from April 1, 1990 through March 31, 1991 for all key Department of Energy (DOE) and DOE contractor operated facilities possessing strategic special nuclear materials. Classified information is not included in this report. This classified information includes data for the Rocky Flats and Y-12 nuclear weapons production facilities or facilities under ID investigation. However, classified ID data from such facilities receive the same scrutiny and analyses as the included data.

Not Available

1992-01-01T23:59:59.000Z

155

High performance materials in coal conversion utilization. Technical progress report, April 1, 1995--June 30, 1995  

SciTech Connect (OSTI)

This is the seventh quarterly report on a three year grant regarding {open_quotes}High Performance Materials in Coal Conversion Utilization.{close_quotes} The grant is for a joint university/industry effort under the US Department of Energy (DOE) University Coal Research Program. The University of Tennessee Space Institute (UTSI) is the prime contractor and The University of Pennsylvania and Lanxide Corporation are subcontractors. UTSI has completed the planned laboratory exposure tests involving pulverized coal slag on the production of Lanxide DIMOX{trademark} ceramic composite material. In addition, the strength testing (at temperature) of C-ring sections of the production composite is complete and the analysis of the data is reported in a thesis which was submitted toward a M.S. degree.

NONE

1995-07-01T23:59:59.000Z

156

Final Report, Materials for Industrial Heat Recovery Systems, Tasks 3 and 4 Materials for Heat Recovery in Recovery Boilers  

SciTech Connect (OSTI)

The DOE-funded project on materials for industrial heat recovery systems included four research tasks: materials for aluminum melting furnace recuperator tubes, materials and operational changes to prevent cracking and corrosion of the co-extruded tubes that form primary air ports in black liquor recovery boilers, the cause of and means to prevent corrosion of carbon steel tubes in the mid-furnace area of recovery boilers, and materials and operational changes to prevent corrosion and cracking of recovery boiler superheater tubes. Results from studies on the latter two topics are given in this report while separate reports on results for the first two tasks have already been published. Accelerated, localized corrosion has been observed in the mid-furnace area of kraft recovery boilers. This corrosion of the carbon steel waterwall tubes is typically observed in the vicinity of the upper level of air ports where the stainless clad co-extruded wall tubes used in the lower portion of the boiler are welded to the carbon steel tubes that extend from this transition point or cut line to the top of the boiler. Corrosion patterns generally vary from one boiler to another depending on boiler design and operating parameters, but the corrosion is almost always found within a few meters of the cut line and often much closer than that. This localized corrosion results in tube wall thinning that can reach the level where the integrity of the tube is at risk. Collection and analysis of gas samples from various areas near the waterwall surface showed reducing and sulfidizing gases were present in the areas where corrosion was accelerated. However, collection of samples from the same areas at intervals over a two year period showed the gaseous environment in the mid-furnace section can cycle between oxidizing and reducing conditions. These fluctuations are thought to be due to gas flow instabilities and they result in an unstable or a less protective scale on the carbon steel tubes. Also, these fluctuating air flow patterns can result in deposition of black liquor on the wall tubes, and during periods when deposition is high, there is a noticeable increase in the concentrations of sulfur-bearing gases like hydrogen sulfide and methyl mercaptan. Laboratory studies have shown that chromized and aluminized surface treatments on carbon steel improve the resistance to sulfidation attack. Studies of superheater corrosion and cracking have included laboratory analyses of cracked tubes, laboratory corrosion studies designed to simulate the superheater environment and field tests to study the movement of superheater tubes and to expose a corrosion probe to assess the corrosion behavior of alternate superheater alloys, particularly alloys that would be used for superheaters operating at higher temperatures and higher pressures than most current boilers. In the laboratory corrosion studies, samples of six alternate materials were immersed in an aggressive, low melting point salt mixture and exposed for times up to 336 h, at temperatures of 510, 530 or 560C in an inert or reactive cover gas. Using weight change and results of metallographic examination, the samples were graded on their resistance to the various environments. For the superheater corrosion probe studies, samples of the same six materials were exposed on an air-cooled corrosion probe exposed in the superheater section of a recovery boiler for 1000 h. Post exposure examination showed cracking and/or subsurface attack in the samples exposed at the higher temperatures with the attack being more severe for samples 13 exposed above the first melting temperature of the deposits that collected on the superheater tubes. From these superheater studies, a ranking was developed for the six materials tested. The task addressing cracking and corrosion of primary air port tubes that was part of this project produced results that have been extensively implemented in recovery boilers in North America, the Nordic countries and many other parts of the world. By utilizing these results, boilers ar

Keiser, James R.; Kish, Joseph R.; Singh, Preet M.; Sarma, Gorti B.; Yuan, Jerry; Gorog, J. Peter; Frederick, Laurie A.; Jette, Francois R.; Meisner, Roberta A.; Singbeil, Douglas L.

2007-12-31T23:59:59.000Z

157

High performance materials in coal conversion utilization. Technical progress report, October 1, 1995--December 31, 1995  

SciTech Connect (OSTI)

This is the ninth quarterly report on a three year grant regarding {open_quotes}High Performance Materials in Coal Conversion Utilization.{close_quotes} The grant is for a joint university/industry effort under the U.S. Department of Energy (DOE) University Coal Research Program. The University of Tennessee Space Institute (UTSI) is the prime contractor and The University of Pennsylvania and Lanxide Corporation are subcontractors. UTSI has completed all the initially planned laboratory exposure tests involving pulverized coal slag on the production Lanxide DIMOX{trademark} ceramic composite material. In addition, the strength testing (at temperature) and analysis of C-ring sections of the exposed production composite is complete. The development of a technique to laser coat the material has been the major activity while awaiting an innovatively produced new test sample. This sample will be tested and compared to the production tubes tested at UTSI.

NONE

1996-01-01T23:59:59.000Z

158

MATERIAL R&D FOR HIGH-INTENSITY PROTON BEAM PROGRESS REPORT  

E-Print Network [OSTI]

MATERIAL R&D FOR HIGH-INTENSITY PROTON BEAM TARGETS PROGRESS REPORT Nick Simos, BNL May 5, 2006 #12-weaved Carbon-Carbon Composite · Toyota "Gum Metal" · Graphite (IG-43) · AlBeMet · Beryllium · Ti Alloy (6Al-4V of it put together in 6 weeks · 3D-weaved Carbon-Carbon Composite · 2D-weaved Carbon-Carbon · Toyota "Gum

McDonald, Kirk

159

High performance materials in coal conversion utilization. Technical progress report, January 1, 1996--March 31, 1996  

SciTech Connect (OSTI)

This is the tenth quarterly report on a three year grant regarding ``High Performance Materials in Coal Conversion Utilization.`` The grant is for a joint university/industry effort under the US Department of Energy (DOE) University Coal Research Program. The University of Tennessee Space Institute (UTSI) is the prime contractor and The University of Pennsylvania and Lanxide Corporation are subcontractors. The object of this grant is to test, analyze, and improve the heat and coal-slag corrosion resistance of a SiC{sub (p)}/Al{sub 2}O{sub 3} ceramic composite tubular material. The material will be evaluated for its ability to withstand the pressures, temperatures and corrosion attack which would be encountered within a coal-fired high-temperature, high pressure air heater. The evaluation includes strength testing at elevated temperatures of production tubes as well as one tube manufactured with an innovative new technology. The feasibility of several joining and coating techniques will also be investigated. UTSI has completed all the initially planned laboratory exposure tests involving pulverized coal slag on the production Lanxide DIMOX{trademark} ceramic composite material. In addition, the strength testing (at temperature) and analysis of C-ring sections of the exposed production composite is complete. The evaluation of a laser-induced coating to laser coat the material has been the major activity this quarter while awaiting an innovatively produced new DIMOX{trademark} test sample.

NONE

1996-04-01T23:59:59.000Z

160

High performance materials in coal conversion utilization. Final report, October 1, 1993--September 30, 1996  

SciTech Connect (OSTI)

This report describes the research conducted at the University of Tennessee Space Institute on high performance materials for use in corrosive environments. The work was supported by a US Department of Energy University Coal Research grant. Particular attention was given to the silicon carbide particulate reinforced alumina matrix ceramic composite manufactured by Lanxide Corporation as a potential tubular component in a coal-fired recuperative high-temperature air heater. Extensive testing was performed to determine the high temperature corrosion effects on the strength of the material. A computer modeling of the corrosion process was attempted but the problem proved to be too complex and was not successful. To simplify the situation, a computer model was successfully produced showing the corrosion thermodynamics involved on a monolithic ceramic under the High Performance Power System (HIPPS) conditions (see Appendix A). To seal the material surface and thus protect the silicon carbide particulate from corrosive attack, a dense non porous alumina coating was applied to the material surface. The coating was induced by a defocused carbon dioxide laser beam. High temperature corrosion and strength tests proved the effectiveness of the coating. The carbon dioxide laser was also used to successfully join two pieces of the Lanxide material, however, resources did not allow for the testing of the resulting joint.

McCay, T.D.; Boss, W.H. [ed.; Dahotre, N. [and others

1996-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "materials clsm reported" 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

Materials  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recovery challenge fund LasDubey selectedContract Research Material

162

Hazardous Materials Verification and Limited Characterization Report on Sodium and Caustic Residuals in Materials and Fuel Complex Facilities MFC-799/799A  

SciTech Connect (OSTI)

This report is a companion to the Facilities Condition and Hazard Assessment for Materials and Fuel Complex Sodium Processing Facilities MFC-799/799A and Nuclear Calibration Laboratory MFC-770C (referred to as the Facilities Condition and Hazards Assessment). This report specifically responds to the requirement of Section 9.2, Item 6, of the Facilities Condition and Hazards Assessment to provide an updated assessment and verification of the residual hazardous materials remaining in the Sodium Processing Facilities processing system. The hazardous materials of concern are sodium and sodium hydroxide (caustic). The information supplied in this report supports the end-point objectives identified in the Transition Plan for Multiple Facilities at the Materials and Fuels Complex, Advanced Test Reactor, Central Facilities Area, and Power Burst Facility, as well as the deactivation and decommissioning critical decision milestone 1, as specified in U.S. Department of Energy Guide 413.3-8, Environmental Management Cleanup Projects. Using a tailored approach and based on information obtained through a combination of process knowledge, emergency management hazardous assessment documentation, and visual inspection, this report provides sufficient detail regarding the quantity of hazardous materials for the purposes of facility transfer; it also provides that further characterization/verification of these materials is unnecessary.

Gary Mecham

2010-08-01T23:59:59.000Z

163

Conceptual design report: Nuclear materials storage facility renovation. Part 7, Estimate data  

SciTech Connect (OSTI)

The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This report is organized according to the sections and subsections outlined by Attachment III-2 of DOE Document AL 4700.1, Project Management System. It is organized into seven parts. This document, Part VII - Estimate Data, contains the project cost estimate information.

NONE

1995-07-14T23:59:59.000Z

164

Conceptual design report: Nuclear materials storage facility renovation. Part 1, Design concept. Part 2, Project management  

SciTech Connect (OSTI)

The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This document provides Part I - Design Concept which describes the selected solution, and Part II - Project Management which describes the management system organization, the elements that make up the system, and the control and reporting system.

NONE

1995-07-14T23:59:59.000Z

165

Secondary materials: Engineering properties, environmental consequences, and social and economic impacts. Final report  

SciTech Connect (OSTI)

This report investigates two secondary materials, plastic lumber made from mixed plastic waste, and cement blocks and structures made with incinerator ash. Engineering properties, environmental impacts, and energy costs and savings of these secondary materials are compared to standard lumber products and cement blocks. Market capacity and social acceptance of plastic lumber and stabilized ash products are analyzed. These secondary materials apparently have potential markets; however, their economic value is primarily that they will not take up landfill space. For plastic lumber and stabilized incinerator ash products, marine and highway construction seem ideal public works applications. Incinerator ash may be suitable to use in seawalls, jetties, fishing reefs, highway barriers, and roadbed applications. Docks, piers, highway sound barriers, parking stops, and park furniture may all be made from plastic lumber. To encourage public acceptance and improve the market potential of secondary materials, these activities could be beneficial: industry should emphasize developing useful, long-lived products; industry and governments should create product performance criteria; government should provide rigorous testing and demonstration programs; and government and industry should cooperate to improve public outreach and educational programs.

Breslin, V.; Reaven, S.; Schwartz, M.; Swanson, L.; Zweig, M.; Bortman, M.; Schubel, J.

1993-08-01T23:59:59.000Z

166

Electromagnetic material changes for remote detection and monitoring: a feasibility study: Progress report  

SciTech Connect (OSTI)

A new concept for radiation detection is proposed, allowing a decoupling of the sensing medium and the readout. An electromagnetic material, such as a magnetic ceramic ferrite, is placed near a source to be tracked such as a shipping container. The electromagnetic material changes its properties, in this case its magnetic permeability, as a function of radiation. This change is evident as a change in reflection frequency and magnitude when probed using a microwave/millimeter-wave source. This brief report discusses modeling of radiation interaction of various candidate materials using a radiation detector modeling code Geant4, system design considerations for the remote readout, and some theory of the material interaction physics. The theory of radiation change in doped magnetic insulator ferrites such as yttrium iron garnet (YIG) seems well founded based on literature documentation of the photomagnetic effect. The literature also suggests sensitivity of permittivity to neutrons in some ferroelectrics. Research to date indicates that experimental demonstration of these effects in the context of radiation detection is warranted.

McCloy, John S.; Jordan, David V.; Kelly, James F.; McMakin, Douglas L.; Johnson, Bradley R.; Campbell, Luke W.

2009-09-01T23:59:59.000Z

167

Regeneration of FGD dry-sorbent materials. Phase I. Final report  

SciTech Connect (OSTI)

Sodium-based sorbent injection directly into the flue gas duct of a coal-burning power plant has been investigated since 1975 by GFETC (using laboratory and pilot plant apparatus) as an SO/sub 2/ control technology. Regeneration of sorbent from spent sorbent material is highly desirable to reduce the sorbent cost, and to alleviate the leaching and potential pollution problems of soluble sodium compounds when disposing of spent sorbent materials in landfills. The work reported herein was initiated to develop a continuous, aqueous-based process for regeneration of sodium carbonate-type sorbents from spent sodium-base sorbent/flyash materials. Specific project objectives are to: (1) retain process simplicity and to avoid difficult process conditions; (2) maximize recovery of sodium from spent sorbents; (3) minimize process costs and energy requirements; (4) maximize reactivity of the regenerated sodium bicarbonate sorbent; and (5) produce process waste materials that may be disposed of in an environmental acceptable manner. The sorbent regeneration process which has been developed during the laboratory investigation (Phase I) of this project may be divided into three parts: (1) leaching of the spent sodium-based sorbent; (2) conversion of the leachate to a NaCl brine; and (3) production of NaHCO/sub 3/ (regenerated sorbent) using commercially-proven Solvay (ammonia-soda) process technology. Significant results from the laboratory study are as given.

Kapsalopoulou, A.J.; Sargent, D.H.; Rissman, E.F.

1982-05-01T23:59:59.000Z

168

High performance materials in coal conversion utilization. Technical progress report, July 1, 1995--September 30, 1995  

SciTech Connect (OSTI)

This is the eighth quarterly report on a three year grant regarding ``High Performance Materials in Coal Conversion Utilization.`` The grant is for a joint university/industry effort under the US Department of Energy (DOE) University Coal Research Program. The University of Tennessee Space Institute (UTSI) is the prime contractor and the University of Pennsylvania and Lanxide Corporation are subcontractors. The object of this grant is to test, analyze, and improve the heat and coal-slag corrosion resistance of a SiC{sub (p)}/Al{sub 2}O{sub 3} ceramic composite tubular material. The material will be evaluated for its ability to withstand the pressures, temperatures and corrosion attack which would be encountered within a coal-fired high-temperature, high pressure air heater. The evaluation includes strength testing at elevated temperatures of production tubes as well as one manufactured with an innovative new technology. The feasibility of several joining and coating techniques are also being investigated. UTSI has completed all the initially planned laboratory exposure tests involving pulverized coal slag on the production Lanxide DIMOX{trademark} ceramic composite material. In addition, the strength testing (at temperature) and analysis of C- ring sections of the exposed production composite are complete.

NONE

1995-10-01T23:59:59.000Z

169

CLEARANCE OF BULK MATERIALS FROM D&D - LIFE AFTER THE NAS REPORT  

SciTech Connect (OSTI)

Lack of consistent free release standards for solid materials has been an issue that has been around for several decades. The Nuclear Regulatory Commission (NRC) has had specific and dose-based standards for the release of liquids and gases for several decades, but no regulatory mechanisms for the release of solid materials from a nuclear power plant. Even though free releases of small quantities of solid materials continue under existing guidelines from operating plants, the regulatory void creates major difficulties for the bulk materials that result from decommissioning projects. For the nation's fleet of nuclear reactors the cost of this regulatory void could be as high as $10 billion. The NRC has recently resumed the enhanced rulemaking process that was originally initiated in 1999 but was deferred pending a study by the National Academy of Sciences (NAS)/National Research Council. The NAS report and recommendations were issued in March 2002 and the NRC decided in October 2002 to resume the rulemaking process. This paper provides an overview of the developments in this area. It specifically discusses the applicability of ANSI N13.12 as a consensus standard that should be seriously considered for adoption as a regulatory standard.

Devgun, Jas S., Ph.D.

2003-02-27T23:59:59.000Z

170

Investigation of test methods, material properties, and processes for solar-cell encapsulants. Annual report  

SciTech Connect (OSTI)

Potentially useful low cost encapsulation materials are evaluated. The goal of the program is to identify, evaluate, test, and recommend encapsulant materials and processes for the production of cost-effective, long life solar cell modules. Technical investigations have concerned the development of advanced cure chemistries for lamination type pottants, the continued evaluation of soil resistant surface treatments, and the results of an accelerated aging test program for the comparison of material stabilities. Experiments are underway to assess the durability and cost effectiveness of coatings for protection of steel. Investigations are continuing with commercial maintenance coatings based on fluorocarbon and silicone-alkyd chemistries. Experiments were conducted to determine the effectiveness of occlusive coatings for wood products such as hard-board. An experimental program continued to determine the usefulness of soil resistant coatings. Primers were evaluated for effectiveness in bonding candidate pottants to outer covers, glass and substate materials. A program of accelerated aging and life predictive strategies is being conducted and data are reported for sunlamp exposure and thermal aging. Supporting activities are also discussed briefly. (LEW)

Willis, P. B.; Baum, B.

1982-07-01T23:59:59.000Z

171

Engineered materials characterization report for the Yucca Mountain Site Characterization Project. Volume 2, Design data  

SciTech Connect (OSTI)

This is Volume 2 of the Engineered Materials Characterization Report which presents the design data for candidate materials needed in fabricating different components for both large and medium multi-purpose canister (MPC) disposal containers, waste packages for containing uncanistered spent fuel (UCF), and defense high-level waste (HLW) glass disposal containers. The UCF waste package consists of a disposal container with a basket therein. It is assumed that the waste packages will incorporate all-metallic multibarrier disposal containers to accommodate medium and large MPCs, ULCF, and HLW glass canisters. Unless otherwise specified, the disposal container designs incorporate an outer corrosion-allowance metal barrier over an inner corrosion-resistant metal barrier. The corrosion-allowance barrier, which will be thicker than the inner corrosion-resistant barrier, is designed to undergo corrosion-induced degradation at a very low rate, thus providing the inner barrier protection from the near-field environment for a prolonged service period.

Konynenburg, R.A.; McCright, R.D. [Lawrence Livermore National Lab., CA (United States); Roy, A.K. [B and W Fuel Co., Lynchburg, VA (United States); Jones, D.A. [Nevada Univ., Reno, NV (United States)

1995-08-01T23:59:59.000Z

172

Final Report: Stability and Novel Properties of Magnetic Materials and Ferromagnet / Insulator Interfaces  

SciTech Connect (OSTI)

We report investigations of the synthesis, structure, and properties of new materials for spintronic applications integrated onto silicon substrates. Our primary focus is materials with very high, negative, intrinsic spin polarization of the density of states at the Fermi level. We have developed a new synthesis method for Fe3O4 thin films through selective oxidation of Fe, resulting in smooth, low-defect density films. We have synthesized Fe4N films and shown that they preferentially oxidize to Fe3O4. When integrated into magnetic tunnel junctions consisting of Fe4N / AlOx / Fe, oxidation at the Fe4N / AlOx interface creates Fe3O4, leading to negative tunneling magnetoresistance (TMR). Oxidation of Fe in nominally symmetric CoFe / AlOx / CoFe also produces Fe3O4 and negative TMR under selected oxidation conditions.

Voyles, Paul [University of Wisconsin, Madison] [University of Wisconsin, Madison

2013-07-24T23:59:59.000Z

173

High performance materials in coal conversion utilization. Technical progress report, April 1, 1994--June 30, 1994  

SciTech Connect (OSTI)

This is the third quarterly report concerning this three year grant on {open_quotes}High Performance Materials in Coal Conversion Utilization.{close_quotes} The grant is for a joint university/industry effort under the US Department of Energy (DOE) University Coal Research Program. The University of Tennessee Space Institute (UTSI) is the prime contractor and The University of Pennsylvania and Lanxide Corporation are subcontractors. UTSI has completed one third of the planned laboratory exposure tests involving pulverized coal slag on the production of Lanxide DIMOS{sup TM} ceramic composite material. The upgrade of the MTS testing machine is underway and the strength testing (at temperature) of C-ring sections of the composite will begin next quarter.

Not Available

1994-10-01T23:59:59.000Z

174

High performance materials in coal conversion utilization. Technical progress report, January 1, 1994--March 31, 1994  

SciTech Connect (OSTI)

This is the second quarterly report concerning this three year grant on {open_quotes}High Performance Materials in Coal Conversion Utilization.{close_quotes} The grant is for a joint university/industry effort under the US Department of Energy (DOE) University Coal Research Program. The University of Tennessee Space Institute (UTSI) is the prime contractor and The University of Pennsylvania and Lanxide Corporation are subcontractors. The administrative details involved in the finalizing of the subcontracts and the acquisition of the cost shared equipment by UTSI and the U of Pa has slowed progress somewhat, however, the project should go smoothly from this point on. Most of the efforts of this quarter have gone toward preparing the equipment and plans for the laboratory tests. Research into the identification of a suitable protective coating based on thermodynamic considerations and the development of techniques for their application as well as joining ceramic materials has been initiated.

Not Available

1994-04-01T23:59:59.000Z

175

A Novel Approach to Materials Development for Advanced Reactor Systems. Annual Report for Year 1  

SciTech Connect (OSTI)

OAK B188 A Novel Approach to Materials Development for Advanced Reactor Systems. Annual Report for Year 1 Year one of this project had three major goals. First, to specify, order and install a new high current ion source for more rapid and stable proton irradiation. Second, to assess the use of chromium pre-enrichment and the combination of cold-work and irradiation hardening in an effort to assess the role of radiation damage in IASCC without the effects of RIS. Third, to initiate irradiation of reactor pressure vessel steel and Zircaloy. Program Achievements for Year One: Progress was made on all 4 tasks in year one.

Was, G.S.; Atzmon, M.; Wang, L.

2000-09-28T23:59:59.000Z

176

Science-Driven Candidate Search for New Scintillator Materials FY 2013 Annual Report  

SciTech Connect (OSTI)

This annual report presents work carried out during Fiscal Year (FY) 2013 at Pacific Northwest National Laboratory (PNNL) under the project entitled Science-Driven Candidate Search for New Scintillator Materials (Project number: PL13-SciDriScintMat-PD05) and led by Dr. Fei Gao. This project is divided into three tasks, namely (1) Ab initio calculations of electronic properties, electronic response functions and secondary particle spectra; (2) Intrinsic response properties, theoretical light yield, and microscopic description of ionization tracks; and (3) Kinetics and efficiency of scintillation: nonlinearity, intrinsic energy resolution, and pulse shape discrimination. Detailed information on the findings and insights obtained in each of these three tasks are provided in this report. Additionally, papers published this fiscal year or currently in review are included in Appendix together with presentations given this fiscal year.

Gao, Fei; Kerisit, Sebastien N.; Xie, YuLong; Wu, Dangxin; Prange, Micah P.; Van Ginhoven, Renee M.; Campbell, Luke W.; Wang, Zhiguo

2013-10-01T23:59:59.000Z

177

Annual report: Purchasing and Materials Management Organization, Sandia National Laboratories, fiscal year 1992  

SciTech Connect (OSTI)

This report summarizes the purchasing and transportation activities of the Purchasing and Materials Management Organization for Fiscal Year 1992. Activities for both the New Mexico and California locations are included. Topics covered in this report include highlights for fiscal year 1992, personnel, procurements (small business procurements, disadvantaged business procurements, woman-owned business procurements, New Mexico commercial business procurements, Bay area commercial business procurements), commitments by states and foreign countries, and transportation activities. Also listed are the twenty-five commercial contractors receiving the largest dollar commitments, commercial contractors receiving commitments of $1,000 or more, integrated contractor and federal agency commitments of $1,000 or more from Sandia National Laboratories/New Mexico and California, and transportation commitments of $1,000 or more from Sandia National Laboratories/New Mexico and California.

Zaeh, R.A.

1993-04-01T23:59:59.000Z

178

Heavy vehicle propulsion system materials program: Semiannual progress report, April 1996--September 1996  

SciTech Connect (OSTI)

The purpose of the Heavy Vehicle Propulsion System Materials Program is the development of materials: ceramics, intermetallics, metal alloys, and metal and ceramic coatings, to support the dieselization of class 1-3 trucks to realize a 35% fuel-economy improvement over current gasoline-fueled trucks and to support commercialization of fuel-flexible LE-55 low-emissions, high-efficiency diesel engines for class 7-8 trucks. The Office of Transportation Technologies, Office of Heavy Vehicle Technologies (OTT OHVT) has an active program to develop the technology for advanced LE-55 diesel engines with 55% efficiency and low emissions levels of 2.0 g/bhp-h NO{sub x} and 0.05 g/bhp-h particulates. The goal is also for the LE-55 engine to run on natural gas with efficiency approaching that of diesel fuel. The LE-55 program is being completed in FY 1997 and, after approximately 10 years of effort, has largely met the program goals of 55% efficiency and low emissions. However, the commercialization of the LE-55 technology requires more durable materials than those that have been used to demonstrate the goals. Heavy Vehicle Propulsion System Materials will, in concert with the heavy duty diesel engine companies, develop the durable materials required to commercialize the LE-55 technologies. OTT OHVT also recognizes a significant opportunity for reduction in petroleum consumption by dieselization of pickup trucks, vans, and sport utility vehicles. Application of the diesel engine to class 1, 2, and 3 trucks is expected to yield a 35% increase in fuel economy per vehicle. The foremost barrier to diesel use in this market is emission control. Once an engine is made certifiable, subsequent challenges will be in cost; noise, vibration, and harshness (NVH); and performance. Separate abstracts have been submitted to the database for contributions to this report.

Johnson, D.R.

1997-04-01T23:59:59.000Z

179

Final Report - Assessment of Potential Phosphate Ion-Cementitious Materials Interactions  

SciTech Connect (OSTI)

The objectives of this limited study were to: (1) review the potential for degradation of cementitious materials due to exposure to high concentrations of phosphate ions; (2) provide an improved understanding of any significant factors that may lead to a requirement to establish exposure limits for concrete structures exposed to soils or ground waters containing high levels of phosphate ions; (3) recommend, as appropriate, whether a limitation on phosphate ion concentration in soils or ground water is required to avoid degradation of concrete structures; and (4) provide a "primer" on factors that can affect the durability of concrete materials and structures in nuclear power plants. An assessment of the potential effects of phosphate ions on cementitious materials was made through a review of the literature, contacts with concrete research personnel, and conduct of a "bench-scale" laboratory investigation. Results of these activities indicate that: no harmful interactions occur between phosphates and cementitious materials unless phosphates are present in the form of phosphoric acid; phosphates have been incorporated into concrete as set retarders, and phosphate cements have been used for infrastructure repair; no standards or guidelines exist pertaining to applications of reinforced concrete structures in high-phosphate environments; interactions of phosphate ions and cementitious materials has not been a concern of the research community; and laboratory results indicate similar performance of specimens cured in phosphate solutions and those cured in a calcium hydroxide solution after exposure periods of up to eighteen months. Relative to the "primer," a separate NUREG report has been prepared that provides a review of pertinent factors that can affect the durability of nuclear power plant reinforced concrete structures.

Naus, Dan J [ORNL; Mattus, Catherine H [ORNL; Dole, Leslie Robert [ORNL

2007-06-01T23:59:59.000Z

180

Evaluation of dry-solids-blend material source for grouts containing 106-AN waste: Final report  

SciTech Connect (OSTI)

Stabilization/solidification technology is one of the most widely used techniques for the treatment and ultimate disposal of both radioactive and chemically hazardous wastes. Cement-based products, commonly referred to as grouts, are the predominant materials of choice because of their low associated processing costs, compatibility with a wide variety of disposal scenarios, and ability to meet stringent processing and performance requirements. Such technology is being utilized in a Grout Treatment Facility (GTF) by the Westinghouse Hanford Company (WHC) for the disposal of various wastes, including 106-AN wastes, located on the Hanford Reservation. The WHC personnel have developed a grout formula for 106-AN disposal that is designed to meet stringent performance requirements. This formula consists of a dry-solids blend containing 40 wt % limestone, 28 wt % granulated blast furnace slag (BFS), 28 wt % American Society for Testing and Materials (ASTM) Class F fly ash, and 4 wt % Type I-II-LA Portland cement. This blend is mixed with 106-AN at a mix ratio of 9 lb of dry-solids blend per gallon of waste. This report documents the final results of efforts at Oak Ridge National Laboratory in support of WHC`s Grout Technology Program to assess the effects of the source of the dry-solids-blend materials on the resulting grout formula.

Spence, R.D.; Gilliam, T.M.; Osborne, S.C.; Francis, C.L.; Trotter, D.R.

1993-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "materials clsm reported" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
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We encourage you to perform a real-time search of NLEBeta
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181

High performance materials in coal conversion utilization. Technical progress report, October 1, 1993--December 31, 1993  

SciTech Connect (OSTI)

This is the first quarterly report for this three year grant on {open_quotes}High Performance Materials in Coal Conversion Utilization.{close_quotes} The grant is a joint university/industry effort under the Department of Energy (DOE) University Coal Research program. The University of Tennessee Space Institute (UTSI) is the prime contractor and The University of Pennsylvania and Lanxide Corporation are subcontractors. It was initially planned to field test ceramic composite tubes furnished by Lanxide Corporation in conjunction with an on-going DOE magnetohydrodynamic (MHD) test series at UTSI. The MHD test program was curtailed due to funding limitations near the beginning of the grant so that the field test portion is now greatly reduced. Bench scale testing will replace most of the field testing. This development should have minimal effect on this research since there is now little interest in the affects of the potassium seeded MHD coal ash on heat exchanger surfaces. The objective is to test and analyze the heat and corrosion resistance of a SiC(p)/Al{sub 2}O{sub 3} ceramic composite tubular material. The material will be evaluated for its ability to withstand the pressures, temperatures and corrosion attack which will be encountered within a coal-fired high-temperature, high-pressure air heater. The evaluation will include strength testing at elevated temperatures.

Not Available

1994-02-01T23:59:59.000Z

182

A regulatory analysis on emergency preparedness for fuel cycle and other radioactive material licensees: Final report  

SciTech Connect (OSTI)

The question this Regulatory Analysis sought to answer is: should the NRC impose additional emergency preparedness requirements on certain fuel cycle and other radioactive material licensees for dealing with accidents that might have offsite releases of radioactive material. To answer the question, we analyzed potential accidents for 15 types of fuel cycle and other radioactive material licensees. An appropriate plan would: (1) identify accidents for which protective actions should be taken by people offsite; (2) list the licensee's responsibilities for each type of accident, including notification of local authorities (fire and police generally); and (3) give sample messages for local authorities including protective action recommendations. This approach more closely follows the approach used for research reactors than for power reactors. The low potential offsite doses (acute fatalities and injuries not possible except possibly for UF/sub 6/ releases), the small areas where actions would be warranted, the small number of people involved, and the fact that the local police and fire departments would be doing essentially the same things they normally do, are all factors that tend to make a simple plan adequate. This report discusses the potentially hazardous accidents, and the likely effects of these accidents in terms of personnel danger.

McGuire, S.A.

1988-01-01T23:59:59.000Z

183

Advanced Researech and Technology Development fossil energy materials program: Semiannual progress report for the period ending September 30, 1988  

SciTech Connect (OSTI)

The objective of the ARandTD Fossil Energy Materials Program is to conduct research and development on materials for fossil energy applications with a focus on the longer-term and generic needs of the various fossil fuel technologies. The program includes research aimed toward a better understanding of materials behavior in fossil energy environments and the development of new materials capable of substantial enhancement of plant operations and reliability. The ORNL Fossil Energy Materials Program Office compiles and issues this combined semiannual progress report from camera-ready copies submitted by each of the participating subcontractor organizations. This report of activities on the program is organized in accordance with a work breakdown structure in which projects are organized according to materials research thrust areas. These areas are (1) Structural Ceramics, (2) Alloy Development and Mechanical Properties, (3) Corrosion and Erosion of Alloys, and (4) Assessments and Technology Transfer. Individual projects are processed separately for the data bases.

Not Available

1989-01-01T23:59:59.000Z

184

Review of PennDOT Publication 408 for the use of recycled co-product materials: Summary recommendations. Final report  

SciTech Connect (OSTI)

The purpose of this project is to decrease the institutional or perceived institutional barriers for the use of recycled and co-product materials including glass, steel slag, foundry sand, fly ash, shingle tabs, reclaimed Portland cement concrete, and scrap tires in the Pennsylvania Department of Transportation`s (PennDOT) Publications 408, Commonwealth of Pennsylvania Department of Transportation Specifications. This report reviews potential uses of each material, identifies the project that used these materials, and provides direction for future specification development.

Van Tassel, E.L.; Tikalsky, P.J.; Christensen, D.W.

1999-04-30T23:59:59.000Z

185

Materials Management Report Request Please Fax Completed Form Back to: 679-1993 or Mail to MC 2012  

E-Print Network [OSTI]

Materials Management Report Request Please Fax Completed Form Back to: 679-1993 or Mail to MC 2012 to the Authorized Employee? (from Box #2) __ Yes __ No FOR MATERIALS & RESOURCE MANAGEMENT OFFICE USE ONLY Ship To Location (5) AUTHORIZED BY: (Department Head or Manager

Oliver, Douglas L.

186

Year 1 Progress Report Computational Materials and Chemical Sciences Network Administration  

SciTech Connect (OSTI)

This document reports progress on the project Computational Materials and Chemical Sciences Network Administration, which is supported by DOE BES Grant DE-FG02-02ER45990 MOD 08. As stated in the original proposal, the primary goal of this project is to carry out the scientific administrative responsibilities for the Computational Materials and Chemical Sciences Network (CMCSN) of the U.S. Department of Energy, Office of Basic Energy Sciences. These responsibilities include organizing meetings, publishing and maintaining CMCSNs website, publishing a periodic newsletter, writing original material for both the website and the newsletter, maintaining CMCSN documentation, editing scientific documents, as needed, serving as liaison for the entire Network, facilitating information exchange across the network, communicating CMCSNs success stories to the larger community and numerous other tasks outside the purview of the scientists in the CMCSN. Given the dramatic increase in computational power, advances in computational materials science can have an enormous impact in science and technology. For many of the questions that can be addressed by computation there is a choice of theoretical techniques available, yet often there is no accepted understanding of the relative strengths and effectiveness of the competing approaches. The CMCSN fosters progress in this understanding by providing modest additional funding to research groups which engage in collaborative activities to develop, compare, and test novel computational techniques. Thus, the CMCSN provides the glue money which enables different groups to work together, building on their existing programs and expertise while avoiding unnecessary duplication of effort. This includes travel funding, partial postdoc salaries, and funding for periodic scientific meetings. The activities supported by this grant are briefly summarized below.

Rehr, John J.

2012-08-02T23:59:59.000Z

187

GNEP Material Transportation, Storage and Disposal Analysis FY-08 Summary Report  

SciTech Connect (OSTI)

This report provides a summary for FY-2008 of activities, analyses and products from the Material Transportation, Storage and Disposal (M-TSD) sub-task of Systems Analysis within the Advanced Fuel Cycle Research & Development area of the Global Nuclear Energy Partnership. The objective of this work is to evaluate near-term material management requirements for initial GNEP facilities and activities, long-term requirements for large-scale GNEP technology deployment, and alternatives and paths forward to meet these needs. For FY-08, the work expanded to include the Integrated Waste Management Strategy as well as integration with the newly formed Waste Forms Campaign. The M-TSD team was expanded with the addition of support from Savannah River National Lab (SRNL) to the existing team of Lawrence Livermore National Lab (LLNL), Argonne National Lab (ANL), Idaho National Lab (INL), Sandia National Lab (SNL) and University of Nevada - Reno (UN-R). During the first half of the year, analysis was focused on providing supporting technical analysis and documentation to support anticipated high-level decisions on program direction. A number of analyses were conducted and reports prepared as program deliverables. This work is briefly summarized in this report. Analyses provided informally to other program efforts are included in this report to provide documentation. This year-end summary was planned primarily as a compilation of activities following the anticipated programmatic decisions. These decisions were deferred beyond the end of the year, and funds were reallocated in a number of areas, thus reducing the M-TSD activities. This report summarizes the miscellaneous 'ad-hoc' work conducted during the later part of the year, such as support to the draft Programmatic Environmental Impact Statement (PEIS), and support to other program studies. Major programmatic contributions from the M-TSD team during the year included: (1) Completion of the IWMS in March 2008 as the baseline for waste management calculations for the GNEP Programmatic Environmental Impact Statement (PEIS). The IWMS represents a collaborative effort between the Systems Analysis, Waste Forms, and Separations Campaigns with contributing authors from multiple laboratories. The IWMS reference is: 'Global Nuclear Energy Partnership Integrated Waste Management Strategy, D. Gombert, INL, et al, GNEP-WAST-WAST-AI-RT-2008-000214, March 2008'. (2) As input to the IWMS and support for program decisions, an evaluation of the current regulatory framework in the U.S. pertaining to the disposal of radioactive wastes under an advanced nuclear fuel cycle was completed by ANL. This evaluation also investigated potential disposal pathways for these wastes. The entire evaluation is provided in Appendix A of this report. (3) Support was provided to the development of the GNEP Programmatic Environmental Impact Statement from INL, SNL and ANL M-TSD staff. (4) M-TSD staff prepared input for DSARR (Dynamic Systems Analysis Report for Nuclear Fuel Recycle) report. The DSARR is an INL led report to examine the time-dependent dynamics for a transition from the current open fuel cycle to either a 1-tier or 2-tier closed fuel cycle. Section 5.3 Waste Management Impacts was provided to INL for incorporation into the DSARR. (5) SNL M-TSD staff prepared a M2 milestone report 'Material Transportation, Storage and Disposal Contribution for Secretarial Decision Package'. The report purpose was to comprehensively evaluate and discuss packaging, storage, and transportation for all potential nuclear and radioactive materials in the process and waste streams being considered by the GNEP program. In particular, a systems view was used to capture all packaging, storage, and transport operations needed to link the various functional aspects of the fuel cycle. (6) SRNL M-TSD staff developed a deliverable report 'Management of Decay Heat from Spent Nuclear Fuel'. This report evaluated a range of options for managing the near-term decay heat associated with Cs and Sr in spent nuclear fuel (SNF) reprocessing waste

Halsey, W

2009-01-15T23:59:59.000Z

188

High Temperature Materials Laboratory fourth annual report, October 1990--September 1991  

SciTech Connect (OSTI)

The High Temperature Materials Laboratory has completed its fourth year of operation as a designated Department of Energy User Facility at the Oak Ridge National Laboratory. Growth of the user program is evidenced by the number of outside institutions who have executed user agreements since the facility began operation in 1987. A total of 118 nonproprietary agreements (62 university and 56 industry) and 28 proprietary agreements (2 university, 26 industry) are now in effect. Five other government facilities have also participated in the user program. Sixty-free nonproprietary research proposals (38 from university, 26 from industry, and 1 other government facility) and four proprietary proposals were considered during this reporting period. Research projects active in FY 1991 are summarized.

Tennery, V.J.; Foust, F.M.

1991-12-01T23:59:59.000Z

189

High Temperature Materials Laboratory sixth annual report, October 1992--September 1993  

SciTech Connect (OSTI)

The High Temperature Materials Laboratory has completed its sixth year of operation as a designated Department of Energy User Facility at the Oak Ridge National Laboratory. Growth of the User Program is evidenced by the number of outside institutions executing user agreements since the facility began operation in 1987. A total of 172 nonproprietary agreements (88 university and 84 industry) and 35 proprietary agreements, (2 university, 33 industry) are now in effect. Six other government facilities have also participated in the User Program. Thirty-eight states are represented by these interactions. Ninety-four nonproprietary research proposals (44 from universities, 47 from industry, and 3 from other government facilities) and three proprietary proposals were considered during this reporting period. Nonproprietary research projects active in FY 1993 are summarized.

Tennery, V.J.; Foust, F.M.

1993-12-01T23:59:59.000Z

190

High Temperature Materials Laboratory fifth annual report, October 1991--September 1992  

SciTech Connect (OSTI)

The High Temperature Materials Laboratory (HTML) has completed its fifth year of operation as a designated Department of Energy (DOE) User Facility at the Oak Ridge National Laboratory (ORNL). Growth of the User Program is evidenced by the number of outside institutions executing user agreements since the facility began operation in 1987. A total of 145 nonproprietary agreements (77 university and 68 industry) and 30 proprietary agreements (2 university, 28 industry) are now in effect. Five other government facilities have also participated in the User Program. Thirty-six states are represented by these interactions. Eighty-one nonproprietary research proposals (44 from university, 36 from industry, and 1 other government facility) and six proprietary proposals were considered during this reporting period. Research projects active in FY 1992 are summarized.

Tennery, V.J.; Foust, F.M.

1992-12-01T23:59:59.000Z

191

20th International Training Course (ITC-20) on the physical protection of nuclear facilities and materials evaluation report.  

SciTech Connect (OSTI)

The goal of this evaluation report is to provide the information necessary to improve the effectiveness of the ITC provided to the International Atomic Energy Agency Member States. This report examines ITC-20 training content, delivery methods, scheduling, and logistics. Ultimately, this report evaluates whether the course provides the knowledge and skills necessary to meet the participants needs in the protection of nuclear materials and facilities.

Ramirez, Amanda Ann

2008-09-01T23:59:59.000Z

192

Closure Report for Corrective Action Unit 392: Spill Sites and Construction Materials, Nevada Test Site, Nevada  

SciTech Connect (OSTI)

This Closure Report documents the closure activities that were conducted to close Corrective Action Unit (CAU) 392--Spill Sites and Construction Materials located on the Nevada Test Site (NTS). CAU 392 is listed on in Appendix III of the Federal Facility Agreement and Consent Order (FFACO) (FFACO, 1996) and consists of the following six Corrective Action Sites (CASs) located in Areas 5 and 6 of the NTS: CAS 05-17-02 Construction Materials/Lead Bricks; CAS 06-17-03 Cement Mud Pit; CAS 06-1 9-01 Cable Pile; Powder Piles (3); CAS 06-44-02 Paint Spill; CAS 06-44-03 Plaster Spill; CAS 06-44-04 Cutting Fluid Discharge Ditch. Closure activities were performed in two phases. Phase 1 activities consisted of collecting waste characterization samples of soil and material present on-site, and where appropriate, performing radiological screening of debris at the six CASs. Results were used to determine how waste generated during closure activities would be handled and disposed of, i.e., as nonhazardous sanitary or hazardous waste, etc. Phase 2 activities consisted of closing each CAS by removing debris and/or soil, disposing of the generated waste, and verifying that each CAS was clean closed by visual inspection and/or by the collecting soil verification samples for laboratory analysis. Copies of the analytical results for the site verification samples are included in Appendix A. Copies of the Sectored Housekeeping Site Closure Verification Form for each of the six CASs are included in Appendix 8. Appendix C contains a copy of the Bechtel Nevada (BN) On-site Waste Transport Manifest for the hazardous waste generated during closure of CAS 06-44-02.

R. B. Jackson

2002-02-01T23:59:59.000Z

193

Thermal and chemical degradation of inorganic membrane materials. Final report, August 1992--May 1995  

SciTech Connect (OSTI)

SRI International conducted a theoretical and experimental program to evaluate the long-term thermal and chemical degradation of inorganic membranes that are being developed to separate the gaseous products of coal gasification. A variety of developmental efforts are underway, including a number of projects sponsored by the US Department of Energy (DOE), to improve the selectivity and permeability of porous inorganic membranes. DOE is also sponsoring efforts to extend the use of metallic membranes to new applications. Most developmental efforts have focused on hydrogen separation by inorganic membranes, which may be used to maximize hydrogen production from coal gas or to remove H{sub 2}S and NH{sub 3} contaminants via thermal or catalytic decomposition in integrated-gasification combined-cycle (IGCC) systems. Inorganic membranes that have a high separation efficiency and exhibit both thermal and chemical stability would improve the economics of power generation from coal. Membrane materials that have been investigated include glass (silica), alumina, carbon, and metals (Pd and Pt). This report describes inorganic membrane materials, long term membrane exposure tests, membrane permeation tests, coal gasifier exposure tests, conclusions, and recommendations.

Damle, A.S.; Krishnan, G.N.; Sanjurjo, A.; Wood, B.J.; Lau, K.H.

1995-05-01T23:59:59.000Z

194

Report of a technical evaluation panel on the use of beryllium for ITER plasma facing material and blanket breeder material  

SciTech Connect (OSTI)

Beryllium because of its low atomic number and high thermal conductivity, is a candidate for both ITER first wall and divertor surfaces. This study addresses the following: why beryllium; design requirements for the ITER divertor; beryllium supply and unirradiated physical/mechanical property database; effects of irradiation on beryllium properties; tritium issues; beryllium health and safety; beryllium-coolant interactions and safety; thermal and mechanical tests; plasma erosion of beryllium; recommended beryllium grades for ITER plasma facing components; proposed manufacturing methods to produce beryllium parts for ITER; emerging beryllium materials; proposed inspection and maintenance techniques for beryllium components and coatings; time table and costs; and the importance of integrating materials and manufacturing personnel with designers.

Ulrickson, M.A. [ed.] [Sandia National Labs., Albuquerque, NM (United States); Manly, W.D. [Oak Ridge National Lab., TN (United States); Dombrowski, D.E. [Brush Wellman, Inc., Cleveland, OH (United States)] [and others

1995-08-01T23:59:59.000Z

195

Science-Driven Candidate Search for New Scintillator Materials: FY 2014 Annual Report  

SciTech Connect (OSTI)

This annual reports presents work carried out during Fiscal Year (FY) 2014 at Pacific Northwest National Laboratory (PNNL) under the project entitled Science-Driven Candidate Search for New Scintillator Materials (Project number: PL13-SciDriScintMat-PD05) and led by Drs. Fei Gao and Sebastien N. Kerisit. This project is divided into three tasks: 1) Ab initio calculations of electronic properties, electronic response functions and secondary particle spectra; 2) Intrinsic response properties, theoretical light yield, and microscopic description of ionization tracks; and 3) Kinetics and efficiency of scintillation: nonproportionality, intrinsic energy resolution, and pulse shape discrimination. Detailed information on the results obtained in each of the three tasks is provided in this Annual Report. Furthermore, peer-reviewed articles published this FY or currently under review and presentations given this FY are included in Appendix. This work was supported by the National Nuclear Security Administration, Office of Nuclear Nonproliferation Research and Development (DNN R&D/NA-22), of the U.S. Department of Energy (DOE).

Kerisit, Sebastien N.; Gao, Fei; Xie, YuLong; Campbell, Luke W.; Wu, Dangxin; Prange, Micah P.

2014-10-01T23:59:59.000Z

196

High Temperature Materials Laboratory eight and ninth annual reports, October 1994 through September 1996  

SciTech Connect (OSTI)

The High Temperature Materials Laboratory (HTML) has completed its ninth year of operation as a designated US Department of Energy User Facility at the Oak Ridge National Laboratory. This document profiles the historical growth of the HTML User and Fellowship Programs since their inception in 1987. Growth of the HTML programs has been demonstrated by the number of institutions executing user agreements, and by the number of days of instrument use (user days) since the HTML began operation. A total of 276 nonproprietary agreements (135 industry, 135 university, and 6 other federal agency) and 56 proprietary agreements are now in effect. This represents an increase of 70 nonproprietary user agreements since the last reporting period (for FY 1994). A state-by-state summary of these nonproprietary user agreements is given in Appendix A, and an alphabetical listing is provided in Appendix B. Forty-four states are represented by these users. During FY 1995 and 1996, the HTML User Program evaluated 145 nonproprietary proposals (62 from industry, 82 from universities, and 1 from other government facilities) and several proprietary proposals. The HTML User Advisory Committee approved about 95% of those proposals, frequently after the prospective user revised the proposal based on comments from the committee. This annual report discusses activities in the individual user centers, as well as plans for the future. It also gives statistics about users, proposals, and publications as well as summaries of the nonproprietary research projects active during 1995 and 1996.

Pasto, A.E.; Russell, B.J.

1997-10-01T23:59:59.000Z

197

High Temperature Materials Laboratory, Eleventh Annual Report: October 1997 through September 1998  

SciTech Connect (OSTI)

The High Temperature Materials Laboratory (HTML) has completed its eleventh year of operation as a designated US Department of Energy User Facility at the Oak Ridge National Laboratory. This document profiles the historical growth of the HTML User and Fellowship Programs since their inception in 1987. Growth of the HTML programs has been demonstrated by the number of institutions executing user agreements and by the number of days of instrument use (user days) since the HTML began operation.A total of 522 agreements (351 industry,156 university,and 15 other federal agency) are now in effect (452 nonproprietary and 70 proprietary). This represents an increase of 75 user agreements since the last reporting period (for FY 1997). A state-by-state summary of the nonproprietary user agreements is given in Appendix A. Forty-six states are represented. During FY 1998, the HTML User Program evaluated 80 nonproprietary proposals (32 from industry, 45 from universities, and 3 from other government facilities) and several proprietary proposals. Appendix B provides a detailed breakdown of the nonproprietary proposals received during FY 1998. The HTML User Advisory Committee approved about 95% of those proposals, sometimes after the prospective user revised the proposal based on comments from the committee. This annual report discusses activities in the individual user centers as well as plans for the future. It also gives statistics about users, proposals, and publications as well as summaries of the nonproprietary research projects active during 1998.

Pasto, A.E.; Russell, B.J.

2000-03-01T23:59:59.000Z

198

Advanced research and technology development fossil energy materials program. Quarterly progress report for the period ending September 30, 1981  

SciTech Connect (OSTI)

This is the fourth combined quarterly progress report for those projects that are part of the Advanced Research and Technology Development Fossil Energy Materials Program. The objective is to conduct a program of research and development on materials for fossil energy applications with a focus on the longer-term and generic needs of the various fossil fuel technologies. The program includes research aimed toward a better understanding of materials behavior in fossil energy environments and the development of new materials capable of substantial enhancement of plant operations and reliability. Work performed on the program generally falls into the Applied Research and Exploratory Development categories as defined in the DOE Technology Base Review, although basic research and engineering development are also conducted. A substantial portion of the work on the AR and TD Fossil Energy Materials Program is performed by participating cntractor organizations. All subcontractor work is monitored by Program staff members at ORNL and Argonne National Laboratory. This report is organized in accordance with a work breakdown structure defined in the AR and TD Fossil Energy Materials Program Plan for FY 1981 in which projects are organized according to fossil energy technologies. We hope this series of AR and TD Fossil Energy Materials Program quarterly progress reports will aid in the dissemination of information developed on the program.

Bradley, R.A. (comp.) [comp.

1981-12-01T23:59:59.000Z

199

Fourth annual progress report on special-purpose materials for magnetically confined fusion reactors  

SciTech Connect (OSTI)

The scope of Special Purpose Materials covers fusion reactor materials problems other than the first-wall and blanket structural materials, which are under the purview of the ADIP, DAFS, and PMI task groups. Components that are considered as special purpose materials include breeding materials, coolants, neutron multipliers, barriers for tritium control, materials for compression and OH coils and waveguides, graphite and SiC, heat-sink materials, ceramics, and materials for high-field (>10-T) superconducting magnets. The Task Group on Special Purpose Materials has limited its concern to crucial and generic materials problems that must be resolved if magnetic-fusion devices are to succeed. Important areas specifically excluded include low-field (8-T) superconductors, fuels for hybrids, and materials for inertial-confinement devices. These areas may be added in the future when funding permits.

Not Available

1982-08-01T23:59:59.000Z

200

Bed material agglomeration during fluidized bed combustion. Technical progress report, January 1, 1993--March 31, 1993  

SciTech Connect (OSTI)

The purpose of this project is to determine the physical and chemical reactions which lead to the undesired agglomeration of bed material during fluidized bed combustion and to relate these reactions to specific causes. A survey of agglomeration and deposit formation in industrial fluidized bed boilers is in progress. Preliminary results indicate that at least five boilers were experiencing some form of bed material agglomeration. In these instances it was observed that large particles were forming within the bed which were larger that the feed. Four operators could confirm that the larger bed particles had formed due to bed particles sticking together or agglomerating. Deposit formation was reported at nine sites with these deposits being found most commonly at coal feed locations and in cyclones. Other deposit locations included side walls and return loops. Examples of these agglomerates and deposits have been received from five of the surveyed facilities. Also during this quarter, a bulk sample of Illinois No. 6 coal was obtained from the Fossil Energy Program at Ames Laboratory here at Iowa State University and prepared for combustion tests. This sample was first ground to a top-size of 3/8`` using a jaw crusher then a size fraction of 3/8`` {times} 8 (US mesh) was then obtained by sieving using a Gilson Test-Master. This size fraction was selected for the preliminary laboratory-scale experiments designed to simulate the dense bed conditions that exist in the bottom of CFB combustors. To ensure uniformity of fuel composition among combustion runs, the sized coal was riffled using, a cone and long row method and stored in bags for each experiment. During this quarter additional modifications were made to achieve better control of fluidization regimes and to aid in monitoring the hydrodynamic and chemical conditions within the reactor.

Brown, R.C.; Dawson, M.R.; Noble, S.D.

1993-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "materials clsm reported" 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

Physical test report to drop test of a 9975 radioactive material shipping packaging  

SciTech Connect (OSTI)

This report presents the drop test results for the 9975 radioactive material shipping package being dropped 30 feet onto a unyielding surface followed by a 40-inch puncture pin drop. The purpose of these drops was to show that the package lid would remain attached to the drum. The 30-foot drop was designed to weaken the lid closure lug while still maintaining maximum extension of the lugs from the drum surface. This was accomplished by angling the drum approximately 30 degrees from horizontal in an inverted position. In this position, the drum was rotated slightly so as not to embed the closure lugs into the drum as a result of the 30-foot drop. It was determined that this orientation would maximize deformation to the closure ring around the closure lug while still maintaining the extension of the lugs from the package surface. The second drop was from 40 inches above a 40-inch tall 6-inch diameter puncture pin. The package was angled 10 degrees from vertical and aligned over the puncture pin to solidly hit the drum lug(s) in an attempt to disengage the lid when dropped.Tests were performed in response to DOE EM-76 review Q5 inquires that questioned the capability of the 9975 drum lid to remain in place under this test sequence. Two packages were dropped utilizing this sequence, a 9974 and 9975. Test results for the 9974 package are reported in WSRC-RP-97-00945. A series of 40-inch puncture pin tests were also performed on undamaged 9975 and 9974 packages.

Blanton, P.S.

1997-11-11T23:59:59.000Z

202

Chemistry and Materials Science progress report, first half FY 1992. Weapons-Supporting Research and Laboratory Directed Research and Development  

SciTech Connect (OSTI)

This report contains sections on: Fundamentals of the physics and processing of metals; interfaces, adhesion, and bonding; energetic materials; plutonium research; synchrotron radiation-based materials science; atomistic approach to the interaction of surfaces with the environment: actinide studies; properties of carbon fibers; buried layer formation using ion implantation; active coherent control of chemical reaction dynamics; inorganic and organic aerogels; synthesis and characterization of melamine-formaldehyde aerogels; structural transformation and precursor phenomena in advanced materials; magnetic ultrathin films, surfaces, and overlayers; ductile-phase toughening of refractory-metal intermetallics; particle-solid interactions; electronic structure evolution of metal clusters; and nanoscale lithography induced chemically or physically by modified scanned probe microscopy.

Not Available

1992-07-01T23:59:59.000Z

203

Process Research of Polycrystalline Silicon Material (PROPSM). Quarterly report No. 1, November 8-December 31, 1983  

SciTech Connect (OSTI)

Recent reported results of hydrogen-passivated polycrystalline silicon solar cells are summarized. Most of the studies have been performed on very small grain or short minority-carrier diffusion length silicon. Hydrogenated solar cells fabricated from this material appear to have effective minority-carrier diffusion lengths that are still not very long, as shown by the open-circuit voltages of passivated cells that are still significantly less than those of single-crystal solar cells. The short-circuit current of solar cells fabricated from large-grain cast polycrystalline silicon is nearly equivalent to that of single-crystal cells, which indicates long bulk minority-carrier diffusion length. However, the open-circuit voltage, which is sensitive to grain boundary recombination, is 20 to 40 mV less. The goal of this program is to minimize the variations in open-circuit voltage and fill-factor that are caused by structural defects by passivating these defects using a hydrogenation process.

Culik, J.S.

1984-01-01T23:59:59.000Z

204

High Temperature Materials Laboratory seventh annual report, October 1993--September 1994  

SciTech Connect (OSTI)

The High Temperature Materials Laboratory (HTML) has completed its seventh year of operation as a designated Department of Energy User Facility at the Oak Ridge National Laboratory. Growth of the User Program has been demonstrated by the number of institutions executing user agreements since the HTML began operation in 1987. A total of 193 nonproprietary agreements (91 industry and 102 university) and 41 proprietary agreements (39 industry and two university) are now in effect. This represents an increase of 21 nonproprietary user agreements during FY 1994. Forty-one states are represented by these users. During FY 1994, the HTML User Program evaluated 106 nonproprietary proposals (46 from industry, 52 from universities, and 8 from other government facilities) and 8 proprietary proposals. The HTML User Advisory Committee approved about ninety-five percent of those evaluated proposals, sometimes after the prospective user revised the proposal based on comments from the Committee. This annual report discusses FY 1994 activities in the individual user centers, as well as plans for the future. It also gives statistics about users and their proposals and FY 1994 publications, and summarizes nonproprietary research projects active in FY 1994.

Tennery, V.J.; Teague, P.A.

1994-12-01T23:59:59.000Z

205

Special-purpose materials for magnetically confined fusion reactors. Third annual progress report  

SciTech Connect (OSTI)

The scope of Special Purpose Materials covers fusion reactor materials problems other than the first-wall and blanket structural materials, which are under the purview of the ADIP, DAFS, and PMI task groups. Components that are considered as special purpose materials include breeding materials, coolants, neutron multipliers, barriers for tritium control, materials for compression and OH coils and waveguides, graphite and SiC, heat-sink materials, ceramics, and materials for high-field (>10-T) superconducting magnets. It is recognized that there will be numerous materials problems that will arise during the design and construction of large magnetic-fusion energy devices such as the Engineering Test Facility (ETF) and Demonstration Reactor (DEMO). Most of these problems will be specific to a particular design or project and are the responsibility of the project, not the Materials and Radiation Effects Branch. Consequently, the Task Group on Special Purpose Materials has limited its concern to crucial and generic materials problems that must be resolved if magnetic-fusion devices are to succeed. Important areas specifically excluded include low-field (8-T) superconductors, fuels for hybrids, and materials for inertial-confinement devices. These areas may be added in the future when funding permits.

Not Available

1981-11-01T23:59:59.000Z

206

AR and TD Fossil Energy Materials Program. Quarterly progress report for the period ending December 31, 1981  

SciTech Connect (OSTI)

The ORNL Fossil Energy Materials Program Office compiles and issues this combined quarterly progress report from camera-ready copies submitted by each of the participating subcontractor organizations. This report of activities on the program is organized in accordance with a work breakdown structure defined in the AR and TD Fossil Energy Materials Program Plan for FY 1982-1986 in which projects are organized according to fossil energy technologies. This report is divided into parts and chapters with each part describing projects related to a particular fossil energy technology. Chapters within a part provide details of the various projects associated with that technology. We hope this series of AR and TD Fossil Energy Materials Program quarterly progress reports will aid in the dissemination of information developed on the program. Plans for the program will be issued annually. A draft of the program plan for FY 1982 to 1986 has been prepared and is in the review process. The implementation of these plans will be reflected by these quarterly progress reports, and this dissemination of information will bw augmented by topical or final reports as appropriate.

Not Available

1982-04-01T23:59:59.000Z

207

UBC Social Ecological Economic Development Studies (SEEDS) Student Report An Investigation into Rapidly Renewable Materials  

E-Print Network [OSTI]

of renewable resources. Renewable resources, whether it is energy or material, are the ones that can be regenerated within a short period time. Rapidly Renewable Materials (RRMs) are examples of such resources into Rapidly Renewable Materials: Bamboo and Cotton Mohammad Hassan Jafarian Thanet (Vic) Ying-udomrat Xiao

208

High Temperature Materials Laboratory 18th Annual Report October 1, 2004 Through September 30, 2005  

SciTech Connect (OSTI)

HTML Annual Report for 10/1/04 - 9/30/05, assigned ORNL Technical Report # ORNL/TM-2006/41. Incorrect number appears in next field.

Pasto, Arvid E [ORNL; Russell, Billie J [ORNL

2006-04-01T23:59:59.000Z

209

Chemistry and materials science progress report. Weapons-supporting research and laboratory directed research and development: FY 1995  

SciTech Connect (OSTI)

This report covers different materials and chemistry research projects carried out a Lawrence Livermore National Laboratory during 1995 in support of nuclear weapons programs and other programs. There are 16 papers supporting weapons research and 12 papers supporting laboratory directed research.

NONE

1996-04-01T23:59:59.000Z

210

Light-water-reactor safety materials engineering research programs. Quarterly progress report, January-March 1985. Volume 1  

SciTech Connect (OSTI)

This progress report summarizes work performed by the Materials Science and Technology Division of Argonne National Laboratory during January, February, and March 1985 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light-Water Reactors and Long-Term Embrittlement of Cast Duplex Stainless Steels in Light-Water-Reactor Systems. 42 refs.

Not Available

1986-03-01T23:59:59.000Z

211

Light-water-reactor safety materials engineering research programs. Volume 3. Quarterly progress report, October-December 1984  

SciTech Connect (OSTI)

This progress report summarizes work performed by the Materials Science and Technology Division of Argonne National Laboratory during October, November, and December 1984 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light-Water Reactors and Long-Term Embrittlement of Cast Duplex Stainless Steels in Light-Water-Reactor Systems.

Not Available

1985-10-01T23:59:59.000Z

212

Preliminary report of the past and present uses, storage, and disposal of hazardous materials at the Lawrence Livermore National Laboratory  

SciTech Connect (OSTI)

This report contains the findings of a records search performed to survey the past and present use, storage, and disposal of hazardous materials and wastes at the Lawrence Livermore National Laboratory (LLNL) site. This report provides a point of departure for further planning of environmental protection activities at the site. This report was conducted using the LLNL archives and library, documents from the US Navy, old LLNL Plant Engineering blueprint files, published articles and reports, Environmental Protection Program records, employee interviews, and available aerial photographs. Sections I and II of this report provide an introduction to the LLNL site and its environmental characteristics. Several tenants have occupied the site prior to the establishment of LLNL, currently operated by the University of California for the US Department of Energy. Section III of this report contains information on environmentally related operations of early site users, the US Navy and California Research and Development. Section IV of this report contains information on the handling of hazardous materials and wastes by LLNL programs. The information is presented in 12 sub-sections, one for each currently operating LLNL program. General site areas, i.e., garbage trenches, the traffic circle landfill, the taxi strip, and old ammunition bunkers are discussed in Section V. 12 refs., 23 figs., 27 tabs.

Dreicer, M.

1985-12-01T23:59:59.000Z

213

Engineered materials characterization report for the Yucca Mountain Site Characterization Project. Volume 1, Introduction, history, and current candidates  

SciTech Connect (OSTI)

The purpose of the Yucca Mountain Site Characterization Project is to evaluate Yucca Mountain for its suitability as a potential site for the nation`s first high-level nuclear waste repository. As part of this effort, Lawrence Livermore National Laboratory (LLNL) has been occupied for a number of years with developing and evaluating the performance of waste packages for the potential repository. In recent years this work has been carried out under the guidance of and in collaboration with the Management and Operating contractor for the Civilian Radioactive Waste Management System, TRW Environmental Safety Systems, Inc., which in turn reports to the Office of Civilian Radioactive Waste Management of the US Department of Energy. This report summarizes the history of the selection and characterization of materials to be used in the engineered barrier system for the potential repository at Yucca Mountain, describes the current candidate materials, presents a compilation of their properties, and summarizes available corrosion data and modeling. The term ``engineered materials`` is intended to distinguish those materials that are used as part of the engineered barrier system from the natural, geologic materials of the site.

Van Konynenburg, R.A.; McCright, R.D.; Roy, A.K.; Jones, D.A.

1995-08-01T23:59:59.000Z

214

MATERIAL R&D FOR HIGH-INTENSITY PROTON BEAM PROGRESS REPORT  

E-Print Network [OSTI]

, 2005 #12;GOAL SEARCH for and evaluate under irradiation environment NEW materials or composites) Load(N) non treated Invar Temp (300 C) Temp (500 C) #12;PHASE II -TARGET MATERIAL R&D · Carbon-Carbon and property measurements) #12;Carbon-Carbon Composite Target Temp. % elongation 23 o C 0% 200 o C -0.023% 400o

McDonald, Kirk

215

University of Illinois at Urbana-Champaign, Materials Research Laboratory progress report for FY 1992  

SciTech Connect (OSTI)

This interdisciplinary laboratory in the College of Engineering support research in areas of condensed matter physics, solid state chemistry, and materials science. These research programs are developed with the assistance of faculty, students, and research associates in the departments of Physics, Materials Science and Engineering, chemistry, Chemical Engineering, Electrical Engineering, Mechanical Engineering, and Nuclear Engineering.

Not Available

1992-07-01T23:59:59.000Z

216

Long Term Materials Test Program. Quarterly progress report, January-March 1980  

SciTech Connect (OSTI)

Objective of the program is to identify corrosion-resistant materials for potential use in a gas turbine. A test rig has been devised for determining the long-term effects of coal-fueled pressurized fluidized-bed combustor exhaust gas on such materials. The test is described. (DLC)

None

1980-04-01T23:59:59.000Z

217

Heavy Vehicle Propulsion System Materials Program semiannual progress report for October 1996 through March 1997  

SciTech Connect (OSTI)

The purpose of the Heavy Vehicle Propulsion System Materials Program is the development of materials: ceramics, intermetallics, metal alloys, and metal and ceramic coatings, to support the dieselization of class 1-3 trucks to realize a 35% fuel-economy improvement over current gasoline-fueled trucks and to support commercialization of fuel-flexible LE-55 low-emissions, high-efficiency diesel engines for class 7-8 trucks. The design of advanced components for high-efficiency diesel engines has, in some cases, pushed the performance envelope for materials of construction past the point of reliable operation. Higher mechanical and tribological stresses and higher temperatures of advanced designs limit the engine designers; advanced materials allow the design of components that may operate reliably at higher stresses and temperatures, thus enabling more efficient engine designs. Advanced materials also offer the opportunity to improve the emissions, NVH, and performance of diesel engines for pickup trucks, vans, and sport utility vehicles. The principal areas of research are: (1) cost effective high performance materials and processing; (2) advanced manufacturing technology; (3) testing and characterization; and (4) materials and testing standards.

NONE

1997-07-01T23:59:59.000Z

218

Materials degradation and fatigue under extreme conditions. Final report, 1 April 1994-31 August 1997  

SciTech Connect (OSTI)

This AFOSR URI addressed complex research problems of materials degradation and fatigue in aerospace structures in severe or extreme environments. A better understanding of materials degradation and flaw initiation dynamics was achieved through a multi-disciplinary research program encompassing chemistry, surface physics, materials science and mechanics, both experimental and theoretical. The Subprojects were as follows: (1) Surface Induced Degradation of Fluorocarbon Lubricants; (2) Molecular Tribology of Perfluoroether Lubricants; (3) Fluids, Including Lubricants Under Extreme Conditions of High Pressure/High Temperature and Confinement; (4) Surface Crack Propagation Under Combined Mechanical and High Pressure Fluid Loading; and (5) Lubricant Assisted Fatigue Crack Growth in Ceramics.

Jonas, J.

1997-10-29T23:59:59.000Z

219

Heavy vehicle propulsion system materials program semiannual progress report for April 1999 through September 1999  

SciTech Connect (OSTI)

The purpose of the Heavy Vehicle Propulsion System Materials Program is the development of materials: ceramics, intermetallics, metal alloys, and metal and ceramic coatings, to support the dieselization of class 1-3 trucks to realize a 35% fuel-economy improvement over current gasoline-fueled trucks and to support commercialization of fuel-flexible LE-55 low-emissions, high-efficiency diesel engines for class 7-8 trucks.

Johnson, D.R.

2000-01-01T23:59:59.000Z

220

Energy Materials Coordinating Committee (EMaCC), Fiscal year 1992. Annual technical report  

SciTech Connect (OSTI)

The DOE EMaCC serves to coordinate the department`s materials programs and to further effective use of materials expertise within the department. This document presents summaries of budgets and of research projects, arranged according to the offices of energy efficiency and renewable energy, energy research, environmental restoration and waste management, nuclear energy, civilian radioactive waste management, defense, and fossil energy. A directory and a keyword index are included.

Not Available

1993-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "materials clsm reported" 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

High performance materials in coal conversion utilization. Technical progress report, April 1, 1996--June 30, 1996  

SciTech Connect (OSTI)

Object is to test, analyze, and improve the heat and coal-slag corrosion resistance of a SiC(p)/Al{sub 2}O{sub 3} ceramic composite tubular material. The material will be evaluated for resistance to pressures, temperatures, and corrosion within a coal-fired high- temperature, high-pressure air heater. Microstructures and some mechanical properties of composite tubes were studied. Other studies include corrosion thermodynamic analysis of Al oxide coated composite.

NONE

1996-07-01T23:59:59.000Z

222

Development & Optimization of Materials and Processes for a Cost Effective Photoelectrochemical Hydrogen Production System. Final report  

SciTech Connect (OSTI)

The overall project objective was to apply high throughput experimentation and combinatorial methods together with novel syntheses to discover and optimize efficient, practical, and economically sustainable materials for photoelectrochemical production of bulk hydrogen from water. Automated electrochemical synthesis and photoelectrochemical screening systems were designed and constructed and used to study a variety of new photoelectrocatalytic materials. We evaluated photocatalytic performance in the dark and under illumination with or without applied bias in a high-throughput manner and did detailed evaluation on many materials. Significant attention was given to ?-Fe2O3 based semiconductor materials and thin films with different dopants were synthesized by co-electrodeposition techniques. Approximately 30 dopants including Al, Zn, Cu, Ni, Co, Cr, Mo, Ti, Pt, etc. were investigated. Hematite thin films doped with Al, Ti, Pt, Cr, and Mo exhibited significant improvements in efficiency for photoelectrochemical water splitting compared with undoped hematite. In several cases we collaborated with theorists who used density functional theory to help explain performance trends and suggest new materials. The best materials were investigated in detail by X-ray diffraction (XRD), scanning electron microscopy (SEM), ultraviolet-visual spectroscopy (UV-Vis), X-ray photoelectron spectroscopy (XPS). The photoelectrocatalytic performance of the thin films was evaluated and their incident photon

McFarland, Eric W

2011-01-17T23:59:59.000Z

223

Ecological fate and effects of solvent-refined-coal (SRC) materials: a status report  

SciTech Connect (OSTI)

Non-occupational health effects associated with SRC operation will be determined by environmental factors governing the form, transport, and persistence of SRC materials and wastes - factors which also mediate exposure to man. Accordingly, the research described is an attempt to determine the fate of disposed solid wastes and spilled SRC materials, and it necessarily focuses on water soluble, persistent materials with greatest potential for mobility and incorporation into water and food supplies. Initially, aqueous equilibrations of SRC-II liquid material and SRC-I nongasified mineral residue were subjected to chemical characterization. Subsequently, laboratory studies were performed on the interaction of aqueous equilibrates of SRC-II liquid and SRC-I non-gasified mineral residue with soil materials isolated suspended sediments, and bottom sediments. These studies were designed to identify effects of specific sorption reactions ion or induced-ion exchange reactions, and toxicity of water soluble, biologically active materials derived from liquid and solid wastes. Results of these experiments have applicability to the environmental fate and effects of biologically active compounds released under different scenarios from product spills and solid waste disposal.

Strand, J.A. III; Vaughan, B.E. (eds.)

1981-10-01T23:59:59.000Z

224

Development of processing techniques for advanced thermal protection materials. Annual progress report, 1 June 1994-31 May 1995  

SciTech Connect (OSTI)

The main purpose of this work has been in the development and characterization of materials for high temperature applications. Thermal Protection Systems (TPS) are constantly being tested, and evaluated for increased thermal shock resistance, high temperature dimensional stability, and tolerance to environmental effects. Materials development was carried out through the use of many different instruments and methods, ranging from extensive elemental analysis to physical attributes testing. The six main focus areas include: (1) protective coatings for carbon/carbon composites; (2) TPS material characterization; (3) improved waterproofing for TPS; (4) modified ceramic insulation for bone implants; (5) improved durability ceramic insulation blankets; and (6) ultra-high temperature ceramics. This report describes the progress made in these research areas during this contract period.

Selvaduray, G.S.

1995-06-01T23:59:59.000Z

225

Metal finishing and vacuum processes groups, Materials Fabrication Division progress report, March-May 1984  

SciTech Connect (OSTI)

Progress is reported in fabrication and coating activities being conducted for the weapons program, nuclear test program, nuclear design program, magnetic fusion program, and miscellaneous applications. (DLC)

Dini, J.W.; Romo, J.G.; Jones, L.M.

1984-07-11T23:59:59.000Z

226

Heavy Vehicle Propulsion System Materials Program Semiannual Progress Report for October 1998 Through March 1999  

SciTech Connect (OSTI)

The purpose of the Heavy Vehicle Propulsion System Materials Program is the development of materials: ceramics, intermetallics, metal alloys, and metal and ceramic coatings, to support the dieselization of class 1-3 trucks to realize a 35% fuel-economy improvement over current gasoline-fueled trucks and to support commercialization of fuel-flexible LE-55 low-emissions, high-efficiency diesel engines for class 7-8 trucks. The Office of Transportation Technologies, Office of Heavy Vehicle Technologies (OIT OHVT) has an active program to develop the technology for advanced LE-55 diesel engines with 55% efficiency and low emissions levels of 2.0 g/bhp-h NOX and 0.05 g/bhp-h particulate. The goal is also for the LE-55 engine to run on natural gas with efficiency approaching that of diesel fuel. The LE-55 program is being completed in FY 1997 and, after approximately 10 years of effort, has largely met the program goals of 55% efficiency and low emissions. However, the commercialization of the LE-55 technology requires more durable materials than those that have been used to demonstrate the goals. Heavy Vehicle Propulsion System Materials will, in concert with the heavy duty diesel engine companies, develop the durable materials required to commercialize the LE-55 technologies. OIT OHVT also recognizes a significant opportunity for reduction in petroleum consumption by dieselization of pickup trucks, vans, and sport utility vehicles. Application of the diesel engine to class 1,2, and 3 trucks is expected to yield a 35% increase in fuel economy per vehicle. The foremost barrier to diesel use in this market is emission control. Once an engine is made certifiable, subsequent challenges will be in cost; noise, vibration, and harshness (NVH); and performance. The design of advanced components for high-efficiency diesel engines has, in some cases, pushed the performance envelope for materials of construction past the point of reliable operation. Higher mechanical and tribological stresses and higher temperatures of advanced designs limit the engine designer; advanced materials allow the design of components that may operate reliably at higher stresses and temperatures, thus enabling more efficient engine designs. Advanced materials also offer the opportunity to improve the emissions, NVH, and performance of diesel engines for pickup trucks, vans, and sport utility vehicles. The principal areas of research are: (1) Cost Effective High Performance Materials and Processing; (2) Advanced Manufacturing Technology; (3)Testing and Characterization; and (4) Materials and Testing Standards.

Johnson, R.D.

1999-06-01T23:59:59.000Z

227

Compilation of reports from research supported by the Materials Engineering Branch, Division of Engineering: 1991--1993. Volume 2  

SciTech Connect (OSTI)

Since 1965, the Materials Engineering Branch, Division of Engineering, of the Nuclear Regulatory Commission`s Office of Nuclear Regulatory Research, and its predecessors dating back to the Atomic Energy Commission (AEC), has sponsored research programs concerning the integrity of the primary system pressure boundary of light water reactors. The components of concern in these research programs have included the reactor pressure vessel (RPV), steam generators, and the piping. These research programs have covered a broad range of topics, including fracture mechanics analysis and experimental work for RPV and piping applications, inspection method development and qualification, and evaluation of irradiation effects to RPV steels. This report provides as complete a listing as practical of formal technical reports submitted to the NRC by the investigators working on these research programs. This listing includes topical, final and progress reports, and is segmented by topic area. In many cases a report will cover several topics (such as in the case of progress reports of multi-faceted programs), but is listed under only one topic. Therefore, in searching for reports on a specific topic, other related topic areas should be checked also. The separate volumes of this report cover the following periods: Volume 1: 1965--1990 and Volume 2: 1991--1993.

Hiser, A.L. [comp.

1994-06-01T23:59:59.000Z

228

Summary report on transportation of nuclear fuel materials in Japan : transportation infrastructure, threats identified in open literature, and physical protection regulations.  

SciTech Connect (OSTI)

This report summarizes the results of three detailed studies of the physical protection systems for the protection of nuclear materials transport in Japan, with an emphasis on the transportation of mixed oxide fuel materials1. The Japanese infrastructure for transporting nuclear fuel materials is addressed in the first section. The second section of this report presents a summary of baseline data from the open literature on the threats of sabotage and theft during the transport of nuclear fuel materials in Japan. The third section summarizes a review of current International Atomic Energy Agency, Japanese and United States guidelines and regulations concerning the physical protection for the transportation of nuclear fuel materials.

Cochran, John Russell; Ouchi, Yuichiro (Japan Atomic Energy Agency, Japan); Furaus, James Phillip; Marincel, Michelle K.

2008-03-01T23:59:59.000Z

229

Final Technical Report for DE-SC0001878 [Theory and Simulation of Defects in Oxide Materials  

SciTech Connect (OSTI)

We explored a wide variety of oxide materials and related problems, including materials at the nanoscale and generic problems associated with oxide materials such as the development of more efficient computational tools to examine these materials. We developed and implemented methods to understand the optical and structural properties of oxides. For ground state properties, our work is predominantly based on pseudopotentials and density functional theory (DFT), including new functionals and going beyond the local density approximation (LDA): LDA+U. To study excited state properties (quasiparticle and optical excitations), we use time dependent density functional theory, the GW approach, and GW plus Bethe-Salpeter equation (GW-BSE) methods based on a many-body Green function approaches. Our work focused on the structural, electronic, optical and magnetic properties of defects (such as oxygen vacancies) in hafnium oxide, titanium oxide (both bulk and clusters) and related materials. We calculated the quasiparticle defect states and charge transition levels of oxygen vacancies in monoclinic hafnia. we presented a milestone G0W0 study of two of the crystalline phases of dye-sensitized TiO{sub 2} clusters. We employed hybrid density functional theory to examine the electronic structure of sexithiophene/ZnO interfaces. To identify the possible effect of epitaxial strain on stabilization of the ferromagnetic state of LaCoO{sub 3} (LCO), we compare the total energy of the magnetic and nonmagnetic states of the strained theoretical bulk structure.

Chelikowsky, James R. [University of Texas at Austin] [University of Texas at Austin

2014-04-14T23:59:59.000Z

230

Heavy vehicle propulsion system materials program semiannual progress report for April 1998 thru September 1998  

SciTech Connect (OSTI)

The purpose of the Heavy Vehicle Propulsion System Materials Program is the development of materials: ceramics, intermetallics, metal alloys, and metal and ceramic coatings, to support the dieselization of class 1--3 trucks to realize a 35{percent} fuel-economy improvement over current gasoline-fueled trucks and to support commercialization of fuel-flexible LE-55 low-emissions, high-efficiency diesel engines for class 7--8 trucks. The Office of Transportation Technologies, Office of Heavy Vehicle Technologies (OTT OHVT) has an active program to develop the technology for advanced LE-55 diesel engines with 55{percent} efficiency and low emissions levels of 2.0 g/bhp-h NO{sub x} and 0.05 g/bhp-h particulates. The goal is also for the LE-55 engine to run on natural gas with efficiency approaching that of diesel fuel. The LE-55 program is being completed in FY 1997 and, after approximately 10 years of effort, has largely met the program goals of 55{percent} efficiency and low emissions. However, the commercialization of the LE-55 technology requires more durable materials than those that have been used to demonstrate the goals. Heavy Vehicle Propulsion System Materials will, in concert with the heavy-duty diesel engine companies, develop the durable materials required to commercialize the LE-55 technologies.

Johnson, D.R.

1999-01-01T23:59:59.000Z

231

Neutron Spectrometry for Identification of filler material in UXO - Final Report  

SciTech Connect (OSTI)

Unexploded ordnance (UXO)-contaminated sites often include ordnance filled with inert substances that were used in dummy rounds. During UXO surveys, it is difficult to determine whether ordnance is filled with explosives or inert material (e.g., concrete, plaster-of-paris, wax, etc.) or is empty. Without verification of the filler material, handling procedures often necessitate that the object be blown in place, which has potential impacts to the environment, personnel, communities and survey costs. The Department of Defense (DoD) needs a reliable, timely, non-intrusive and cost-effective way to identify filler material before a removal action. A new technology that serves this purpose would minimize environmental impacts, personnel safety risks and removal costs; and, thus, would be especially beneficial to remediation activities.

Bliss, Mary

2007-09-12T23:59:59.000Z

232

Bed material agglomeration during fluidized bed combustion. Technical progress report, September 30, 1992--December 31, 1992  

SciTech Connect (OSTI)

The purpose of this project is to determine the physical and chemical reactions which led to the undesired agglomeration of bed material during fluidized bed combustion and to relate these reactions to specific causes. Survey of industrial-scale fluidized bed combustors is being conducted to determine the occurrence of bed agglomeration and the circumstances under which agglomeration took place. This task should be finished by the end of February. Samples of bed material, agglomerate material, and boiler deposits are being requested from boiler operators as part of the survey. Once received, these sample will be analyzed to determine chemical and mineralogic composition. The bulk chemical determination will be performed using x-ray fluorescence and inductively coupled plasma-optical emission (ICP). Mineralogy will be detected by x-ray diffraction (XRD). Chemical and mineral reactions will be determined by scanning electron microscopy, optical microscopy, and electron microprobe.

Brown, R.C.; Dawson, M.R.; Noble, S.

1993-02-01T23:59:59.000Z

233

Conceptual design report: Nuclear materials storage facility renovation. Part 3, Supplemental information  

SciTech Connect (OSTI)

The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. It is organized into seven parts. Part I - Design Concept describes the selected solution. Part III - Supplemental Information contains calculations for the various disciplines as well as other supporting information and analyses.

NONE

1995-07-14T23:59:59.000Z

234

Draft Workshop Report: 30 June 2004 Workshop on Advanced Computational Materials Science  

E-Print Network [OSTI]

power plants represent an even greater challenge to structural materials development and application and simulation could help bridge the gap between the data that is needed to support the implementation for significantly higher operating temperatures than the current generation of LWRs to obtain higher thermal

Gropp, Bill

235

Investigation of test methods, material properties, and processes for solar cell encapsulants. Annual report  

SciTech Connect (OSTI)

The goal of this program is to identify, evaluate, and recommend encapsulant materials and processes for the production of cost-effective, long-life solar cell modules. Technical activities during the past year have covered a number of topics and have emphasized the development of solar module encapsulation technology that employs ethylene/vinyl acetate, copolymer (EVA) as the pottant. These activities have included: (1) continued production of encapsulation grade EVA in sheet form to meet the needs of the photovoltaic industry; (2) investigations of three non-blocking techniques for EVA sheet; (3) performed an economic analysis of the high volume production of each pottant in order to estimate the large volume selling price (EVA, EPDM, aliphatic urethane, PVC plastisol, and butyl acrylate); (4) initiated an experimental corrosion protection program to determine if metal components could be successfully protected by encapsulation; (5) began an investigation to determine the maximum temperature which can be tolerated by the candidate pottant material in the event of hot spot heating or other temperature override; (6) continuation of surveys of potentially useful outer cover materials; and (7) continued with the accelerated artificial weathering of candidate encapsulation materials. Study results are presented. (WHK)

Willis, P. B.; Baum, B.; Schnitzer, H. S.

1980-07-01T23:59:59.000Z

236

Annual Report of the EURATOM/UKAEA Fusion Programme 2006/07 7 Materials and Technology  

E-Print Network [OSTI]

­ production and release of a new version (EASY- 2007) of the European Activation System. Many System (EASY). A Materials Modelling and Validation The impact of high energy neutrons on the atoms understanding of these processes, in order to accelerate the development of fusion by guiding the optimisation

237

Energy Resolved High Resolution Dynamic E-Cell Materials Research. Final Report  

SciTech Connect (OSTI)

The purpose of this project was to develop in situ materials reaction observation capability in an intermediate voltage high resolution transmission electron microscope. To accomplish this we purchased a GATAN imaging energy filter system, a hot stage, and designed and constructed an environmental cell and real time television image recording system, and installed this equipment on our EM 430 intermediate voltage electron microscope.

Carpenter, Ray; Sharma, Renu; Mayer, James

2000-05-16T23:59:59.000Z

238

Annual Report 2010 Page 1 PHYSICS AND MATERIALS SCIENCE RESEARCH UNIT (PHYMS)  

E-Print Network [OSTI]

chalcopyrites and kesterites, aiming at low cost and high efficiency. Fundamental semiconductor physicsMS comprises: Physics of Advanced Materials LPM, Soft Condensed Matter Physics TSCM and Photovoltaics LPV. Its of nanomagnets. TSCM, the group for Theory of Soft Condensed Matter, was built up in 2010. The topic of research

van der Torre, Leon

239

Final Report of Optimization Algorithms for Hierarchical Problems, with Applications to Nanoporous Materials  

SciTech Connect (OSTI)

The research focuses on the modeling and optimization of nanoporous materials. In systems with hierarchical structure that we consider, the physics changes as the scale of the problem is reduced and it can be important to account for physics at the fine level to obtain accurate approximations at coarser levels. For example, nanoporous materials hold promise for energy production and storage. A significant issue is the fabrication of channels within these materials to allow rapid diffusion through the material. One goal of our research is to apply optimization methods to the design of nanoporous materials. Such problems are large and challenging, with hierarchical structure that we believe can be exploited, and with a large range of important scales, down to atomistic. This requires research on large-scale optimization for systems that exhibit different physics at different scales, and the development of algorithms applicable to designing nanoporous materials for many important applications in energy production, storage, distribution, and use. Our research has two major research thrusts. The first is hierarchical modeling. We plan to develop and study hierarchical optimization models for nanoporous materials. The models have hierarchical structure, and attempt to balance the conflicting aims of model fidelity and computational tractability. In addition, we analyze the general hierarchical model, as well as the specific application models, to determine their properties, particularly those properties that are relevant to the hierarchical optimization algorithms. The second thrust was to develop, analyze, and implement a class of hierarchical optimization algorithms, and apply them to the hierarchical models we have developed. We adapted and extended the optimization-based multigrid algorithms of Lewis and Nash to the optimization models exemplified by the hierarchical optimization model. This class of multigrid algorithms has been shown to be a powerful tool for solving discretized optimization models. Our optimization models are multi-level models, however. They are more general, involving different governing equations at each level. A major aspect of this project was the development of flexible software that can be used to solve a variety of hierarchical optimization problems.

Nash, Stephen G.

2013-11-11T23:59:59.000Z

240

Basic Research Needs for Materials Under Extreme Environments. Report of the Basic Energy Sciences Workshop on Materials Under Extreme Environments, June 11-13, 2007  

SciTech Connect (OSTI)

To evaluate the potential for developing revolutionary new materials that will meet demanding future energy requirements that expose materials to environmental extremes.

Wadsworth, J.; Crabtree, G. W.; Hemley, R. J.; Falcone, R.; Robertson, I.; Stringer, J.; Tortorelli, P.; Gray, G. T.; Nicol, M.; Lehr, J.; Tozer, S. W.; Diaz de la Rubia, T.; Fitzsimmons, T.; Vetrano, J. S.; Ashton, C. L.; Kitts, S.; Landson, C.; Campbell, B.; Gruzalski, G.; Stevens, D.

2008-02-01T23:59:59.000Z

Note: This page contains sample records for the topic "materials clsm reported" 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

Final Scientific/Technical Report for DOE/EERE project Advanced Magnetic Refrigerant Materials  

SciTech Connect (OSTI)

A team led by GE Global Research developed new magnetic refrigerant materials needed to enhance the commercialization potential of residential appliances such as refrigerators and air conditioners based on the magnetocaloric effect (a nonvapor compression cooling cycle). The new magnetic refrigerant materials have potentially better performance at lower cost than existing materials, increasing technology readiness level. The performance target of the new magnetocaloric material was to reduce the magnetic field needed to achieve 4 C adiabatic temperature change from 1.5 Tesla to 0.75 Tesla. Such a reduction in field minimizes the cost of the magnet assembly needed for a magnetic refrigerator. Such a reduction in magnet assembly cost is crucial to achieving commercialization of magnetic refrigerator technology. This project was organized as an iterative alloy development effort with a parallel material modeling task being performed at George Washington University. Four families of novel magnetocaloric alloys were identified, screened, and assessed for their performance potential in a magnetic refrigeration cycle. Compositions from three of the alloy families were manufactured into regenerator components. At the beginning of the project a previously studied magnetocaloric alloy was selected for manufacturing into the first regenerator component. Each of the regenerators was tested in magnetic refrigerator prototypes at a subcontractor at at GE Appliances. The property targets for operating temperature range, operating temperature control, magnetic field sensitivity, and corrosion resistance were met. The targets for adiabatic temperature change and thermal hysteresis were not met. The high thermal hysteresis also prevented the regenerator components from displaying measurable cooling power when tested in prototype magnetic refrigerators. Magnetic refrigerant alloy compositions that were predicted to have low hysteresis were not attainable with conventional alloy processing methods. Preliminary experiments with rapid solidification methods showed a path towards attaining low hysteresis compositions should this alloy development effort be continued.

Johnson, Francis

2014-06-30T23:59:59.000Z

242

Propulsion system materials program. Semiannual progress report, October 1995--March 1996  

SciTech Connect (OSTI)

This portion of the program is identified as program element 1.0 within the work breakdown structure (WBS). It contains five subelements: (1) Monolithics, (2) Ceramic Composites, (3) Thermal and Wear Coatings, (4) Joining, and (5) Ceramic Machining. Ceramic research conducted within the Monolithics subelement currently includes work activities on low Cost Si{sub 3}N{sub 4} powder, green state ceramic fabrication, characterization, and densification, and on structural, mechanical, and physical properties of these ceramics. Research conducted within the Ceramic Composites subelement currently includes silicon nitride and oxide-based composites, and low expansion materials. Research conducted in the Thermal and Wear Coatings subelement is currently limited to oxide-based coatings and involves coating synthesis, characterization, and determination of the mechanical and physical properties of the coatings. Research conducted in the Joining subelement currently includes studies of processes to produce strong, stable joints between zirconia ceramics and iron-base alloys. As part of an expanded effort to reduce the cost of ceramic components, a new initiative in cost effective machining has been started. A major objective of the research in the Materials and Processing program element is to systematically advance the understanding of the relationships between ceramic raw materials such as powders and reactant gases, the processing variables involved in producing the ceramic materials, and the resultant microstructures and physical and mechanical properties of the ceramic materials. Success in meeting this objective will provide U.S. companies with new or improved ways for producing economical, highly reliable ceramic components for advanced heat engines.

Johnson, D.R.

1996-07-01T23:59:59.000Z

243

Testing of organic waste surrogate materials in support of the Hanford organic tank program. Final report  

SciTech Connect (OSTI)

To address safety issues regarding effective waste management efforts of underground organic waste storage tanks at the Hanford Site, the Bureau of Mines conducted a series of tests, at the request of the Westinghouse Hanford company. In this battery of tests, the thermal and explosive characteristics of surrogate materials, chosen by Hanford, were determined. The surrogate materials were mixtures of inorganic and organic sodium salts, representing fuels and oxidants. The oxidants were sodium nitrate and sodium nitrite. The fuels were sodium salts of oxalate, citrate and ethylenediamine tetraacetic acid (EDTA). Polyethylene powder was also used as a fuel with the oxidant(s). Sodium aluminate was used as a diluent. In addition, a sample of FeCN, supplied by Hanford was also investigated.

Turner, D.A. [Westinghouse Hanford Co., Richland, WA (United States); Miron, Y. [Bureau of Mines (United States)

1994-01-01T23:59:59.000Z

244

Strategic partnerships final LDRD report : nanocomposite materials for efficient solar hydrogen production.  

SciTech Connect (OSTI)

This 'campus executive' project sought to advance solar thermochemical technology for producing the chemical fuels. The project advanced the common interest of Sandia National Laboratories and the University of Arizona in creating a sustainable and viable alternative to fossil fuels. The focus of this effort was in developing new methods for creating unique monolithic composite structures and characterizing their performance in thermochemical production of hydrogen from water. The development and processing of the materials was undertaken in the Materials Science and Engineering Department at the University of Arizona; Sandia National Laboratories performed the thermochemical characterization. Ferrite/yttria-stabilized zirconia composite monoliths were fabricated and shown to have exceptionally high utilization of the ferrite for splitting CO{sub 2} to obtain CO (a process analogous to splitting H{sub 2}O to obtain H{sub 2}).

Corral, Erica L. (University of Arizona, Tucson, AZ); Miller, James Edward; Walker, Luke S. (University of Arizona, Tucson, AZ); Evans, Lindsey R.

2012-05-01T23:59:59.000Z

245

Conceptual design report, Hazardous Materials Management and Emergency Response (HAMMER) Training Center  

SciTech Connect (OSTI)

For the next 30 years, the main activities at the US Department of Energy (DOE) Hanford Site will involve the management, handling, and cleanup of toxic substances. If the DOE is to meet its high standards of safety, the thousands of workers involved in these activities will need systematic training appropriate to their tasks and the risks associated with these tasks. Furthermore, emergency response for DOE shipments is the primary responsibility of state, tribal, and local governments. A collaborative training initiative with the DOE will strengthen emergency response at the Hanford Site and within the regional communities. Local and international labor has joined the Hazardous Materials Management and Emergency Response (HAMMER) partnership, and will share in the HAMMER Training Center core programs and facilities using their own specialized trainers and training programs. The HAMMER Training Center will provide a centralized regional site dedicated to the training of hazardous material, emergency response, and fire fighting personnel.

Kelly, K.E. [Westinghouse Hanford Co., Richland, WA (United States)] [Westinghouse Hanford Co., Richland, WA (United States)

1994-11-09T23:59:59.000Z

246

Enforcement actions: Significant actions resolved material licensees. Semiannual progress report, July--December 1996  

SciTech Connect (OSTI)

This compilation summarizes significant enforcement actions that have been resolved during the period and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to material licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication.

NONE

1997-04-01T23:59:59.000Z

247

Management of radioactive material safety programs at medical facilities. Final report  

SciTech Connect (OSTI)

A Task Force, comprising eight US Nuclear Regulatory Commission and two Agreement State program staff members, developed the guidance contained in this report. This report describes a systematic approach for effectively managing radiation safety programs at medical facilities. This is accomplished by defining and emphasizing the roles of an institution`s executive management, radiation safety committee, and radiation safety officer. Various aspects of program management are discussed and guidance is offered on selecting the radiation safety officer, determining adequate resources for the program, using such contractual services as consultants and service companies, conducting audits, and establishing the roles of authorized users and supervised individuals; NRC`s reporting and notification requirements are discussed, and a general description is given of how NRC`s licensing, inspection and enforcement programs work.

Camper, L.W.; Schlueter, J.; Woods, S. [and others

1997-05-01T23:59:59.000Z

248

Progress report on the accelerator production of tritium materials irradiation program  

SciTech Connect (OSTI)

The Accelerator Production of Tritium (APT) project is developing an accelerator and a spoliation neutron source capable of producing tritium through neutron capture on He-3. A high atomic weight target is used to produce neutrons that are then multiplied and moderated in a blanket prior to capture. Materials used in the target and blanket region of an APT facility will be subjected to several different and mixed particle radiation environments; high energy protons (1-2 GeV), protons in the 20 MeV range, high energy neutrons, and low energy neutrons, depending on position in the target and blanket. Flux levels exceed 10{sup 14}/cm{sup 2}s in some areas. The APT project is sponsoring an irradiation damage effects program that will generate the first data-base for materials exposed to high energy particles typical of spallation neutron sources. The program includes a number of candidate materials in small specimen and model component form and uses the Los Alamos Spallation Radiation Effects Facility (LASREF) at the 800 MeV, Los Alamos Neutron Science Center (LANSCE) accelerator.

Maloy, S.A.; Sommer, W.F.; Brown, R.D.; Roberts, J.E. [and others

1997-05-01T23:59:59.000Z

249

Final Report: Characterization of Hydrogen Adsorption in Carbon-Based Materials by NMR  

SciTech Connect (OSTI)

In support of DOE/EERE's Fuel Cell Technologies Program Hydrogen Sorption Center of Excellence (HSCoE), UNC conducted Nuclear Magnetic Resonance (NMR) measurements that contributed spectroscopic information as well as quantitative analysis of adsorption processes. While NMR based Langmuir isotherms produce reliable H2 capacity measurements, the most astute contribution to the center is provided by information on dihydrogen adsorption on the scale of nanometers, including the molecular dynamics of hydrogen in micropores, and the diffusion of dihydrogen between macro and micro pores. A new method to assess the pore width using H2 as probe of the pore geometry was developed and is based on the variation of the observed chemical shift of adsorbed dihydrogen as function of H2 pressure. Adsorbents designed and synthesized by the Center were assessed for their H2 capacity, the binding energy of the adsorption site, their pore structure and their ability to release H2. Feedback to the materials groups was provided to improve the materials properties. To enable in situ NMR measurements as a function of H2 pressure and temperature, a unique, specialized NMR system was designed and built. Pressure can be varied between 10-4 and 107 Pa while the temperature can be controlled between 77K and room temperature. In addition to the 1H investigation of the H2 adsorption process, NMR was implemented to measure the atomic content of substituted elements, e.g. boron in boron substituted graphitic material as well as to determine the local environment and symmetry of these substituted nuclei. The primary findings by UNC are the following: Boron substituted for carbon in graphitic material in the planar BC3 configuration enhances the binding energy for adsorbed hydrogen. Arrested kinetics of H2 was observed below 130K in the same boron substituted carbon samples that combine enhanced binding energy with micropore structure. Hydrogen storage material made from activated PEEK is well suited for hydrogen storage due to its controlled microporous structure and large surface area. A new porosimetry method for evaluating the pore landscape using H2 as a probe was developed. 1H NMR can probe the nanoscale pore structure of synthesized material and can assess the pore dimension over a range covering 1.2 nm to 2.5 nm, the size that is desired for H2 adsorption. Analysis of 1H NMR spectra in conjunction with the characterization of the bonding structure of the adsorbent by 13C NMR distinguishes between a heterogeneous and homogeneous pore structure as evidenced by the work on AX21 and activated PEEK. Most of the sorbents studied are suited to hydrogen storage at low temperature (T < 100K). Of the materials investigated, only boron substituted graphite has the potential to work at higher temperatures if the boron content in the favorable planar BC3 configuration that actively contributes to adsorption can be increased.

Yue Wu; Alfred Kleinhammes

2011-07-11T23:59:59.000Z

250

Probabilistic accident consequence uncertainty analysis -- Uncertainty assessment for deposited material and external doses. Volume 1: Main report  

SciTech Connect (OSTI)

The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed in 1990. These codes estimate the consequence from the accidental releases of radiological material from hypothesized accidents at nuclear installations. In 1991, the US Nuclear Regulatory Commission and the Commission of the European Communities began cosponsoring a joint uncertainty analysis of the two codes. The ultimate objective of this joint effort was to systematically develop credible and traceable uncertainty distributions for the respective code input variables. A formal expert judgment elicitation and evaluation process was identified as the best technology available for developing a library of uncertainty distributions for these consequence parameters. This report focuses on the results of the study to develop distribution for variables related to the MACCS and COSYMA deposited material and external dose models.

Goossens, L.H.J.; Kraan, B.C.P.; Cooke, R.M. [Delft Univ. of Technology (Netherlands); Boardman, J. [AEA Technology (United Kingdom); Jones, J.A. [National Radiological Protection Board (United Kingdom); Harper, F.T.; Young, M.L. [Sandia National Labs., Albuquerque, NM (United States); Hora, S.C. [Univ. of Hawaii, Hilo, HI (United States)

1997-12-01T23:59:59.000Z

251

UCSB final report for the CSQ program: Review of decoherence and materials physics for superconducting qubits  

E-Print Network [OSTI]

for superconducting qubits John M. Martinis and A. Megrant University of California Santa Barbara (Dated: October 18, 2014) We review progress at UCSB on understanding the physics of decoherence in superconducting qubits report for a five-year program at IARPA on coherent superconducting qubits (CSQ). It summarizes our

Martinis, John M.

252

Materials science division light-water-reactor safety research program. Quarterly progress report, October - December 1981  

SciTech Connect (OSTI)

This progress report summarizes the Argonne National Laboratory work performed during October, November, and December 1981 on water-reactor-safety problems. The research and development areas covered are environmentally assisted cracking in light water reactors, transient fuel response and fission-product release, and clad properties for code verification.

Not Available

1982-05-01T23:59:59.000Z

253

Propulsion System Materials Program semiannual progress report for April 1995 through September 1995  

SciTech Connect (OSTI)

Significant accomplishments in fabricating ceramic components for the DOE, NASA, and DOD advanced heat engine programs have provided evidence that the operation of ceramic parts in high-temperature engine environments is feasible. These programs have also demonstrated that additional research is needed in materials and processing development, design methodology, and data base and life prediction before industry will have a sufficient technology base from which to produce reliable cost-effective ceramic engine components commercially. An assessment of needs was completed, and a 5-year program plan was developed with extensive input from private industry. During the course of the Propulsion System Materials Program, remarkable progress has been made in the development of reliable structural ceramics. However, further work is needed to reduce the cost of ceramics to facilitate their commercial introduction, especially in the highly cost-sensitive automotive market. To this end, the direction of the Propulsion System Materials Program is now shifting toward reducing the cost of ceramics to facilitate commercial introduction of ceramic components for near-term engine applications. In response to extensive input from industry, the plan is to extend the engine types which were previously supported to include near-term (5--10 years) applications in conventional automobile and diesel truck engines. To facilitate the rapid transfer of this technology to US industry, the major portion of the work is being done in the ceramic industry, with technological support from government laboratories, other industrial laboratories, and universities. A systematic approach to reducing the cost of components is envisioned. The work elements are as follows: economic cost modeling, ceramic machining, powder synthesis, alternative forming and densification processes, yield improvement, system design studies, standards development, low-expansion ceramics, and testing and data base development.

NONE

1996-04-01T23:59:59.000Z

254

Hazardous materials in aquatic environments of the Mississippi River Basin. Quarterly project status report, October 1, 1993--December 31, 1993  

SciTech Connect (OSTI)

This quarterly project status report discusses research projects being conducted on hazardous materials in aquatic environments of the Mississippi River basin. We continued to seek improvement in our methods of communication and interactions to support the inter-disciplinary, inter-university collaborators within this program. In addition to the defined collaborative research teams, there is increasing interaction among investigators across projects. Planning for the second year of the project has included the development of our internal request for proposals, and refining the review process for selection of proposals for funding.

Not Available

1993-12-31T23:59:59.000Z

255

Materials Science Clean Room Facility at Tulane University (Final Technical Report)  

SciTech Connect (OSTI)

The project involves conversion of a 3,000 sq. ft. area into a clean room facility for materials science research. It will be accomplished in phases. Phase I will involve preparation of the existing space, acquisition and installation of clean room equipped with a pulsed laser deposition (PLD) processing system, and conversion of ancillary space to facilitate the interface with the clean room. From a capital perspective, Phases II and III will involve the acquisition of additional processing, fabrication, and characterization equipment and capabilities.

Altiero, Nicholas

2014-10-28T23:59:59.000Z

256

Silicon-germanium/gallium phosphide material in high power density thermoelectric modules. Final report, February 1980--September 1981  

SciTech Connect (OSTI)

This is the final report of work on the characterization of an improved Si-Ge alloy and the fabrication of thermoelectric devices. The improved Si-Ge alloy uses a small addition of GaP in n- and p- type 80 at.% Si-20 at.% Ge; this addition reduces the thermal conductivity, thereby increasing its figure of merit and conversion efficiency. The thermoelectric devices fabricated include multicouples intended for use in Radioisotope Thermoelectric Generators (RTGs) and ring-type modules intended for use with nuclear reactor heat sources. This report summarizes the effort in the material as well as the device areas and discusses individual phases of each area. Results should form basis for further effort.

Not Available

1981-12-31T23:59:59.000Z

257

OTEC biofouling, corrosion, and materials program. Progress report, March 1978-March 1981  

SciTech Connect (OSTI)

Argonne National Laboratory has been responsible for the technical management of the OTEC Biofouling, Corrosion, and Materials Program since March 1978. By March of 1981, sensitive field-usable heat-transfer monitors had been developed, extensive open ocean testing had been done, a considerable understanding of the microbiofouling problem had been developed, and commercial methods of removal had been shown to be effective. As a material of construction for heat exchangers, titanium showed excellent corrosion resistance. New grades of stainless steel also showed excellent corrosion resistance, while the most common grades suffered from pitting and/or crevice corrosion. The best aluminum alloys and Alclads showed no pitting and moderate declining corrosion rates under optimum conditions in warm seawater, but were subject to accelerated attack from stagnant water, crevices, abrasive treatment, and ammoniated water; in cold seawater, limited data showed very good behavior. Copper-nickel alloys were similar to aluminum alloys in corrosion rate and were subject to accelerated attack from the same factors; ammonia had a particularly severe effect on these alloys.

Draley, J.E.

1981-09-01T23:59:59.000Z

258

Materials technology for coal-conversion processes. Progress report, April-June 1981  

SciTech Connect (OSTI)

Materials research activities have included work in the areas of coal-slag/refractory interactions, ultrasonic erosion monitoring of metals, fluid acoustics, high-temperature gaseous corrosion of metal alloys, and failure analysis. Work on coal-slag/refractory interaction has included the design of a gas-fired rotating-drum dynamic-slag corrosion test furnace. Field tests on the high-pressure loop (1 1/4-in. 321 SS piping) at the Solvent Refined Coal Liquefaction Pilot Plant were terminated because of excessive erosive wear (1.27 mm lost). Longitudinal and shear-wave velocity measurements from room temperature to 540/sup 0/C were obtained on Types 304, 304L, 316, 347, and 410 stainless steels, Fe-2 1/4Cr-1Mo steel, Stellite 6B, Haynes metal, cold-rolled steel, and cast stainless steel. Work on the fluid-acoustic test loop included changing all seals at the flange joints and calibrating the volumetric flowmeter by using an ASME orifice plate installed in the test section. Agreement within 10% was achieved. The loop has now been cycled several dozen times over a wide range of flow rates. Corrosion experiments have been conducted to evaluate the influence of combustion gas stoichiometry and deposits, such as CaSO/sub 4/, on the corrosion behavior of materials for use as air and steam heat-exchanger tubes. Analyses of failed components from the Grand Forks Energy Technology Center's Slagging Coal-gasification Pilot Plant have been completed.

Not Available

1981-09-01T23:59:59.000Z

259

Progress Report 2011: Understanding compound phase transitions in Heusler alloy giant magnetocaloric materials  

SciTech Connect (OSTI)

Our goal is to gain insight into the fundamental physics that is responsible for magnetocaloric effects (MCE) and related properties at the atomic level. We are currently conducting a systematic study on the effects of atomic substitutions in Ni2MnGa-based alloys, and also exploring related full- and half-Heusler alloys, for example Ni-Mn-X (X=In, Sn, Sb), that exhibit a wide variety of interesting and potentially useful physical phenomena. It is already known that the magnetocaloric effect in the Heusler alloys is fundamentally connected to other interesting phenomena such as shape-memory properties. And the large magnetic entropy change in Ni2Mn0.75Cu0.25Ga has been attributed to the coupling of the first-order, martensitic transition with the second-order ferromagneticâ??paramagnetic (FM-PM) transition. Our research to this point has focused on understanding the fundamental physics at the origin of these complex, compound phase transitions, and the novel properties that emerge. We synthesize the materials using a variety of techniques, and explore their material properties through structural, magnetic, transport, and thermo-magnetic measurements.

Shane Stadler

2011-12-13T23:59:59.000Z

260

Long term materials test program. Quarterly report, October-December 1983  

SciTech Connect (OSTI)

The long-term exposure of gas turbine vane and blade base alloys and a variety of protective coating systems to the effluent from a pressurized fluidized bed coal combustor has reached 4398 hours. After 4053 hours, FeCrAlY overlay coatings and platinum/rhodium-aluminide pack diffusion coatings show excellent resistance to corrosion attack at 1500/sup 0/F. Cobalt-base coatings are somewhat more susceptible to hot corrosion, and the unprotected nickel and cobalt-base alloys are most susceptible to corrosion, although corrosion rates have decreased to less than 1 mil/1000 hours for all materials at 1500/sup 0/F; i.e., corrosion penetration data is evolving parabolically. The three-stage cyclone cleanup system became severely distorted after approximately 5600 hours total service life. Distortion of the cyclones contributed to an increased dust loading to the material test sections, 110 to 250 ppM versus normal loadings of 30 to 90 ppM, for a period of about 75 hours. This increase in dust loading caused severe erosion of the airfoils in the high-velocity test section. Metal recession ranged 4 to 18 mils of leading edge loss on the impulse airfoils, and 11 to 27 mils of leading edge loss on the reaction airfoils. A new three-stage cyclone system was installed and dust loadings now range from 15 to 45 ppM.

Not Available

1984-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "materials clsm reported" 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

INFORMATION: Inspection Report on "Removal of Categories I and II Special Nuclear Material from Sandia National Laboratories-New Mexico"  

SciTech Connect (OSTI)

The Department of Energy's (DOE's) Sandia National Laboratories-New Mexico (Sandia) develops science-based technologies in support of national security in areas such as nuclear weapons, nonproliferation, military technologies, and homeland security. Sandia's primary mission is ensuring that the U.S. nuclear arsenal is safe, secure, and reliable and can fully support the Nation's deterrence policy. Part of this mission includes systems engineering of nuclear weapons; research, design, and development of non-nuclear components; manufacturing of non-nuclear weapons components; the provision of safety, security, and reliability assessments of stockpile weapons; and the conduct of high-explosives research and development and environmental testing. Sandia Corporation, a subsidiary of Lockheed Martin Corporation, operates Sandia for the National Nuclear Security Administration (NNSA). On May 7, 2004, the Secretary announced that the Department would evaluate missions at DOE sites to consolidate Special Nuclear Material (SNM) in the most secure environments possible. The Administrator of the NNSA said that this effort was a key part of an overall plan to transform the nuclear weapons complex into a smaller, safer, more secure, and more efficient national security enterprise. In February 2008, Sandia was the first site to report it had reduced its on-site inventory of nuclear material below 'Categories I and II' levels, which require the highest level of security to protect material such as plutonium and highly enriched uranium. The Office of Inspector General initiated an inspection to determine if Sandia made appropriate adjustments to its security posture in response to the removal of the Categories I and II SNM. We found that Sandia adjusted its security posture in response to the removal of Categories I and II SNM. For example, security posts were closed; unneeded protective force weapons and equipment were excessed from the site; and, Sandia's Site Safeguards and Security Plan was modified. We also found that some highly enriched uranium in a complex material configuration was not removed from Sandia. This material was designated as Category III material using a methodology for assessing the attractiveness of complex materials that was not specifically addressed in any current DOE directive. Although DOE and NNSA officials believed that this designation was appropriate, the methodology used to support this designation had not, as of the time of our review, been incorporated into the DOE directives system. Historically, the Department has considered the categorization of SNM to be an important national security and public policy issue. Consequently, we believe that expedited action should be taken to formalize this methodology in the DOE directives system and that it be disseminated throughout the Department of Energy complex.

None

2010-01-01T23:59:59.000Z

262

Synchrotron studies of narrow band materials. Progress report, July 1, 1991--June 30, 1992  

SciTech Connect (OSTI)

Since last year, we have had three 3-week blocks of beamtime, in April and November 1991 and February 1992, on the Ames/Montana beamline at the Wisconsin Synchrotron Radiation Center (SRC). These runs continued our program on high temperature superconductors, heavy Fermion and related uranium and rare earth materials, and started some work on transition metal oxides. We have also had beamtime at the Brookhaven NSLS, 5 days of beamtime on the Dragon monochromator, beamline U4B, studying resonant photoemission of transition metal oxides using photon energies around the transition metal 2p edges. Data from past runs has been analyzed, and in some cases combined with photoemission and bremsstrahlung isochromat spectroscopy (BIS) data taken in the home U-M lab. 1 fig.

Not Available

1992-07-01T23:59:59.000Z

263

Bipolar plate materials in molten carbonate fuel cells. Final CRADA report.  

SciTech Connect (OSTI)

Advantages of implementation of power plants based on electrochemical reactions are successfully demonstrated in the USA and Japan. One of the msot promising types of fuel cells (FC) is a type of high temperature fuel cells. At present, thanks to the efforts of the leading countries that develop fuel cell technologies power plants on the basis of molten carbonate fuel cells (MCFC) and solid oxide fuel cells (SOFC) are really close to commercialization. One of the problems that are to be solved for practical implementation of MCFC and SOFC is a problem of corrosion of metal components of stacks that are assembled of a number of fuel cells. One of the major components of MCFC and SOFC stacks is a bipolar separator plate (BSP) that performs several functions - it is separation of reactant gas flows sealing of the joints between fuel cells, and current collection from the surface of electrodes. The goal of Task 1 of the project is to develop new cost-effective nickel coatings for the Russian 20X23H18 steel for an MCFC bipolar separator plate using technological processes usually implemented to apply corrosion stable coatings onto the metal parts for products in the defense. There was planned the research on production of nickel coatings using different methods, first of all the galvanic one and the explosion cladding one. As a result of the works, 0.4 x 712 x 1296 mm plates coated with nickel on one side were to be made and passed to ANL. A line of 4 galvanic baths 600 liters was to be built for the galvanic coating applications. The goal of Task 2 of the project is the development of a new material of an MCFC bipolar separator plate with an upgraded corrosion stability, and development of a technology to produce cold roll sheets of this material the sizes of which will be 0.8 x 712x 1296 mm. As a result of these works, a pilot batch of the rolled material in sheets 0.8 x 712 x 1296 mm in size is to be made (in accordance with the norms and standards of the Russian metallurgical industry) and supplied to the partner for tests in a stack of fuel cells. A feasibility study on the cost of the Russian material for a BSP is to be done on Tasks 1, 2 in case the annual order makes up 400,000 sheets. The goal of Task 3 of the project is to research on possible implementation of cermet compositions on the basis of LiAlO{sub 2}, TiN, B{sub 4}C, ceramics with Ni and Ni-Mo binders. BaCeO{sub 3} conductive ceramics with metal binders of Ni, Ni-Cr etc. were also planned to be studied. As a result of these works, a pilot batch of samples is to be made and passed to FCE for tests. The goal of Task 4 of the Project is development of a new alloy or alloys with a ceramic coating that will have upgraded corrosion stability in operation within a SOFC. A new alloy was to be worked out by the way of modification of compositions of industrial alloys. Ceramic coatings are to be applied onto ferrite steel produced serially by iron and steel industry of Russia as sheet iron.

Krumpelt, M.

2004-06-01T23:59:59.000Z

264

Investigations on deflagration to detonation transition in porous energetic materials. Final report  

SciTech Connect (OSTI)

The research carried out by this contract was part of a larger effort funded by LANL in the areas of deflagration to detonation in porous energetic materials (DDT) and detonation shock dynamics in high explosives (DSD). In the first three years of the contract the major focus was on DDT. However, some researchers were carried out on DSD theory and numerical implementation. In the last two years the principal focus of the contract was on DSD theory and numerical implementation. However, during the second period some work was also carried out on DDT. The paper discusses DDT modeling and DSD modeling. Abstracts are included on the following topics: modeling deflagration to detonation; DSD theory; DSD wave front tracking; and DSD program burn implementation.

Stewart, D.S. [Univ. of Illinois, Urbana, IL (United States)

1999-07-01T23:59:59.000Z

265

High power laser and materials investigation. Final report, 31 July 1978-28 October 1979  

SciTech Connect (OSTI)

This is a combined study of resonant pumped solid state lasers as fusion drivers, and the development of crystalline optical materials suitable for propagation of the high peak powers associated with laser fusion research. During this period of study the concept of rare gas halide lasers was first demonstrated by the lasing of Tm:YLF at 453 nm pumped by the 353 nm energy of XeF. Excited stata densities of 5 x 10/sup 18/ cm/sup -3/ have been attained and spectroscopic measurements show that up to 60% of the pump energy can be converted into useful stored energy. Alternative lasers and pumping schemes are also discussed. In all cases the potential RGH/SS systems are evaluated in respect to internal efficiency and heat loading.

Chicklis, E.P.; Folweiler, R.C.; Pollak, T.M.; Baer, J.

1980-06-01T23:59:59.000Z

266

FIFTH STATUS REPORT: TESTING OF AGED SOFTWOOD FIBERBOARD MATERIAL FOR THE 9975 SHIPPING PACKAGE  

SciTech Connect (OSTI)

Samples have been prepared from a 9975 lower fiberboard subassembly fabricated from softwood fiberboard. Physical, mechanical and thermal properties have been measured following varying periods of conditioning in each of several environments. These tests have been conducted in the same manner as previous testing on cane fiberboard samples. Overall, similar aging trends are observed for softwood and cane fiberboard samples, with a few differences. Some softwood fiberboard properties tend to degrade faster in elevated humidity environments, while some cane fiberboard properties degrade faster in the hotter dry environments. As a result, it is premature to assume both materials will age at the same rates, and the preliminary aging models developed for cane fiberboard might not apply to softwood fiberboard. However, it is expected that both cane and softwood fiberboard assemblies will perform satisfactorily in conforming packages stored in a typical KAC storage environment for up to 15 years. Aging and testing of softwood fiberboard will continue and additional data will be collected. Additional samples will be added to each aging environment, to support development of an aging model specific to softwood fiberboard. Post-conditioning data have been measured on samples from a single softwood fiberboard assembly, and baseline data are also available from a limited number of vendor-provided samples. This provides minimal information on the possible sample-to-sample variation exhibited by softwood fiberboard. Data to date are generally consistent with the range seen in cane fiberboard, but some portions of the data trends are skewed toward the lower end of that range. Two additional softwood fiberboard source packages have been obtained and will begin to provide data on the range of variability of this material.

Daugherty, W.; Skidmore, E.; Dunn, K.

2014-04-15T23:59:59.000Z

267

[Research at and operation of the material science x-ray absorption beamline (X-11) at the National Synchrotron Light Source]. Progress report  

SciTech Connect (OSTI)

This report discusses three projects at the Material Science X-Ray Absorption Beamline. Topics discussed include: XAFS study of some titanium silicon and germanium compounds; initial XAS results of zirconium/silicon reactions; and low angle electron yield detector.

Not Available

1992-08-01T23:59:59.000Z

268

Development and application of material and energy balance regularities for renewable energy resources. Final report  

SciTech Connect (OSTI)

The characterization of renewable energy resources is necessary in order to make mass and energy balances for processes which use these substances. This work is concerned with the identification of regularities associated with organic compounds and renewable energy resources. The carbon weight fraction, the reductance degree or equivalents of available electrons per gram atom carbon, the heat of combustion per gram equivalent of available electrons, and the free energy of combustion per gram equivalent of available electrons are investigated. Values of these regularities are reported for organic compounds and renewable resources. 31 references, 4 figures, 48 tables.

Erickson, L.E.; Patel, S.A.

1981-01-01T23:59:59.000Z

269

Survey of the degradation modes of candidate materials for high-level radioactive waste disposal containers. Final report  

SciTech Connect (OSTI)

One of the most significant factors impacting the performance of waste package container materials under repository relevant conditions is the thermal environment. This environment will be affected by the areal power density of the repository, which is dictated by facility design, and the dominant heat transfer mechanism at the site. The near-field environment will evolve as radioactive decay decreases the thermal output of each waste package. Recent calculations (Buscheck and Nitao, 1994) have addressed the importance of thermal loading conditions on waste package performance at the Yucca Mountain site. If a relatively low repository thermal loading design is employed, the temperature and relative humidity near the waste package may significantly affect the degradation of corrosion allowance barriers due to moist air oxidation and radiolytically enhanced corrosion. The purpose this report is to present a literature review of the potential degradation modes for moderately corrosion resistant nickel copper and nickel based candidate materials that may be applicable as alternate barriers for the ACD systems in the Yucca Mountain environment. This report presents a review of the corrosion of nickel-copper alloys, summaries of experimental evaluations of oxidation and atmospheric corrosion in nickel-copper alloys, views of experimental studies of aqueous corrosion in nickel copper alloys, a brief review of galvanic corrosion effects and a summary of stress corrosion cracking in these alloys.

Vinson, D.W.; Bullen, D.B. [Iowa State Univ. of Science and Technology, Ames, IA (United States)

1995-09-22T23:59:59.000Z

270

Process feasibility study in support of silicon material Task I. Final report, October 1, 1975-February 6, 1981  

SciTech Connect (OSTI)

The Low-Cost Solar Array (LSA) Project is directed toward effective cost reduction in the production of silicon for solar cells. Results are presented for process system properties, chemical engineering and economic analyses of the new technologies and processes being developed for the production of lower cost silicon for solar cells. Major physical, thermodynamic and transport property data are reported for the following silicon source and processing chemical materials: silane, silicon tetrachloride, trichlorosilane, dichlorosilane, silicon tetrafluoride, and silicon. The property data are reported for critical temperature, critical pressure, critical volume, vapor pressure, heat of vaporization, heat capacity, density, surface tension, viscosity, thermal conductivity, heat of formation and Gibb's free energy of formation. Chemical engineering analyses involving the preliminary process design of a plant (1000 MT/yr capacity) to produce silicon via the technology under consideration were accomplished for the following processes: UCC silane process for silicon, BCL process for silicon, conventional polysilicon process (Siemens technology), SiI/sub 4/ decomposition process, and DCS process (dichlorosilane).Major activities in chemical engineering analyses include base case conditions, reaction chemistry, process flowsheet, material balance, energy balance, property data, equipment design, major equipment list, production labor and forward for economic analysis. The process design package provides detailed data for raw materials, utilities, major process equipment and production labor requirements necessary for polysilicon production in each process. Using detailed data from the process design package, economic analyses for a 1000 MT/yr silicon plant were accomplished. Primary results from the economic analyses included plant capital investment and product cost. Results are presented and discussed. (WHK)

Yaws, C.L.; Li, K.Y.; Hopper, J.R.; Fang, C.S.; Hansen, K.C.

1981-02-06T23:59:59.000Z

271

Efficiency Improvement of Nitride-Based Solid State Light Emitting Materials -- CRADA Final Report  

SciTech Connect (OSTI)

The development of In{sub x}Ga{sub 1-x} N/GaN thin film growth by Molecular Beam Epitaxy has opened a new route towards energy efficient solid-state lighting. Blue and green LED's became available that can be used to match the whole color spectrum of visible light with the potential to match the eye response curve. Moreover, the efficiency of such devices largely exceeds that of incandescent light sources (tungsten filaments) and even competes favorably with lighting by fluorescent lamps. It is, however, also seen in Figure 1 that it is essential to improve on the luminous performance of green LED's in order to mimic the eye response curve. This lack of sufficiently efficient green LED's relates to particularities of the In{sub x}Ga{sub 1-x}N materials system. This ternary alloy system is polar and large strain is generated during a lattice mismatched thin film growth because of the significantly different lattice parameters between GaN and InN and common substrates such as sapphire. Moreover, it is challenging to incorporate indium into GaN at typical growth temperatures because a miscibility gap exists that can be modified by strain effects. As a result a large parameter space needs exploration to optimize the growth of In{sub x}Ga{sub 1-x}N and to date it is unclear what the detailed physical processes are that affect device efficiencies. In particular, an inhomogeneous distribution indium in GaN modifies the device performance in an unpredictable manner. As a result technology is pushed forward on a trial and error basis in particular in Asian countries such as Japan and Korea, which dominate the market and it is desirable to strengthen the competitiveness of the US industry. This CRADA was initiated to help Lumileds Lighting/USA boosting the performance of their green LED's. The tasks address the distribution of the indium atoms in the active area of their blue and green LED's and its relation to internal and external quantum efficiencies. Procedures to measure the indium distribution with near atomic resolution were developed and applied to test samples and devices that were provided by Lumilids. Further, the optical performance of the device materials was probed by photoluminescence, electroluminescence and time resolved optical measurements. Overall, the programs objective is to provide a physical basis for the development of a simulation program that helps making predictions to improve the growth processes such that the device efficiency can be increased to about 20%. Our study addresses all proposed aspects successfully. Carrier localization, lifetime and recombination as well as the strain-induced generation of electric fields were characterized and modeled. Band gap parameters and their relation to the indium distribution were characterized and modeled. Electron microscopy was developed as a unique tool to measure the formation of indium clusters on a nanometer length scale and it was demonstrated that strain induced atom column displacements can reliably be determined in any materials system with a precision that approaches 2 pm. The relation between the local indium composition x and the strain induced lattice constant c(x) in fully strained In{sub x}Ga{sub 1-x}N quantum wells was found to be: c(x) = 0.5185 + {alpha}x with {alpha} = 0.111 nm. It was concluded that the local indium concentration in the final product can be modulated by growth procedures in a predictable manner to favorably affect external quantum efficiencies that approached target values and that internal quantum efficiencies exceeded them.

Kisielowski, Christian; Weber, Eicke

2010-05-13T23:59:59.000Z

272

Development of New Low-Cost, High-Performance, PV Module Encapsulant/Packaging Materials: Final Technical Progress Report, 22 October 2002 - 15 November 2007  

SciTech Connect (OSTI)

Report on objectives to work with U.S.-based PV module manufacturers (c-Si, a-Si, CIS, other thin films) to develop/qualify new low-cost, high-performance PV module encapsulant/packaging materials, and processes using the packaging materials.

Tucker, R.

2008-04-01T23:59:59.000Z

273

Final Scientific Report, New Proton Conductive Composite Materials for PEM Fuel Cells  

SciTech Connect (OSTI)

This project covered one of the main challenges in present-day PEM fuel cell technology: to design a membrane capable of maintaining high conductivity and mechanical integrity when temperature is elevated and water vapor pressure is severely reduced. The DOE conductivity milestone of 0.1 S cm-1 at 120 degrees C and 50 % relative humidity (RH) for designed membranes addressed the target for the project. Our approach presumed to develop a composite membrane with hydrophilic proton-conductive inorganic material and the proton conductive polymeric matrix that is able to bridge the conduction paths in the membrane. The unique aspect of our approach was the use of highly functionalized inorganic additives to benefit from their water retention properties and high conductivity as well. A promising result turns out that highly hydrophilic phosphorsilicate gels added in Nafion matrix improved PEM fuel cell performance by over 50% compared with bare Nafion membrane at 120 degrees C and 50 % RH. This achievement realizes that the fuel cell operating pressure can be kept low, which would make the PEM fuel cell much more cost efficient and adaptable to practical operating conditions and facilitate its faster commercialization particularly in automotive and stationary applications.

Lvov, Serguei

2010-11-08T23:59:59.000Z

274

Closure Report for Corrective Action Unit 166: Storage Yards and Contaminated Materials, Nevada Test Site, Nevada  

SciTech Connect (OSTI)

Corrective Action Unit (CAU) 166 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Storage Yards and Contaminated Materials' and consists of the following seven Corrective Action Sites (CASs), located in Areas 2, 3, 5, and 18 of the Nevada Test Site: CAS 02-42-01, Condo Release Storage Yd - North; CAS 02-42-02, Condo Release Storage Yd - South; CAS 02-99-10, D-38 Storage Area; CAS 03-42-01, Conditional Release Storage Yard; CAS 05-19-02, Contaminated Soil and Drum; CAS 18-01-01, Aboveground Storage Tank; and CAS 18-99-03, Wax Piles/Oil Stain. Closure activities were conducted from March to July 2009 according to the FF ACO (1996, as amended February 2008) and the Corrective Action Plan for CAU 166 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007b). The corrective action alternatives included No Further Action and Clean Closure. Closure activities are summarized. CAU 166, Storage Yards and Contaminated Materials, consists of seven CASs in Areas 2, 3, 5, and 18 of the NTS. The closure alternatives included No Further Action and Clean Closure. This CR provides a summary of completed closure activities, documentation of waste disposal, and confirmation that remediation goals were met. The following site closure activities were performed at CAU 166 as documented in this CR: (1) At CAS 02-99-10, D-38 Storage Area, approximately 40 gal of lead shot were removed and are currently pending treatment and disposal as MW, and approximately 50 small pieces of DU were removed and disposed as LLW. (2) At CAS 03-42-01, Conditional Release Storage Yard, approximately 7.5 yd{sup 3} of soil impacted with lead and Am-241 were removed and disposed as LLW. As a BMP, approximately 22 ft{sup 3} of asbestos tile were removed from a portable building and disposed as ALLW, approximately 55 gal of oil were drained from accumulators and are currently pending disposal as HW, the portable building was removed and disposed as LLW, and accumulators, gas cylinders, and associated debris were removed and are currently pending treatment and disposal as MW. (3) At CAS 05-19-02, Contaminated Soil and Drum, as a BMP, an empty drum was removed and disposed as sanitary waste. (4) At CAS 18-01-01, Aboveground Storage Tank, approximately 165 gal of lead-impacted liquid were removed and are currently pending disposal as HW, and approximately 10 gal of lead shot and 6 yd{sup 3} of wax embedded with lead shot were removed and are currently pending treatment and disposal as MW. As a BMP, approximately 0.5 yd{sup 3} of wax were removed and disposed as hydrocarbon waste, approximately 55 gal of liquid were removed and disposed as sanitary waste, and two metal containers were grouted in place. (5) At CAS 18-99-03, Wax Piles/Oil Stain, no further action was required; however, as a BMP, approximately l.5 yd{sup 3} of wax were removed and disposed as hydrocarbon waste, and one metal container was grouted in place.

NSTec Environmental Restoration

2009-08-01T23:59:59.000Z

275

Division of Development and Technology Plasma/Materials Interaction and High Heat Flux Materials and Components Task Groups: Report on the joint meeting, July 9, 1986  

SciTech Connect (OSTI)

This paper contains a collection of viewgraphs from a joint meeting of the Division of Development and Technology Plasma/Materials Interaction and High Heat Flux Materials and Components Task Groups. A list of contributing topics is: PPPL update, ATF update, Los Alamos RFP program update, status of DIII-D, PMI graphite studies at ORNL, PMI studies for low atomic number materials, high heat flux materials issues, high heat flux testing program, particle confinement in tokamaks, helium self pumping, self-regenerating coatings technical planning activity and international collaboration update. (LSP)

Watson, R.D. (ed.)

1986-09-01T23:59:59.000Z

276

Nuclear Energy Plant Optimization (NEPO) final report on aging and condition monitoring of low-voltage cable materials.  

SciTech Connect (OSTI)

This report summarizes results generated on a 5-year cable-aging program that constituted part of the Nuclear Energy Plant Optimization (NEPO) program, an effort cosponsored by the U. S. Department of Energy (DOE) and the Electric Power Research Institute (EPRI). The NEPO cable-aging effort concentrated on two important issues involving the development of better lifetime prediction methods as well as the development and testing of novel cable condition-monitoring (CM) techniques. To address improved life prediction methods, we first describe the use of time-temperature superposition principles, indicating how this approach improves the testing of the Arrhenius model by utilizing all of the experimentally generated data instead of a few selected and processed data points. Although reasonable superposition is often found, we show several cases where non-superposition is evident, a situation that violates the constant acceleration assumption normally used in accelerated aging studies. Long-term aging results over extended temperature ranges allow us to show that curvature in Arrhenius plots for elongation is a common occurrence. In all cases the curvature results in a lowering of the Arrhenius activation energy at lower temperatures implying that typical extrapolation of high temperature results over-estimates material lifetimes. The long-term results also allow us to test the significance of extrapolating through the crystalline melting point of semi-crystalline materials. By utilizing ultrasensitive oxygen consumption (UOC) measurements, we show that it is possible to probe the low temperature extrapolation region normally inaccessible to conventional accelerated aging studies. This allows the quantitative testing of the often-used Arrhenius extrapolation assumption. Such testing indicates that many materials again show evidence of ''downward'' curvature (E{sub a} values drop as the aging temperature is lowered) consistent with the limited elongation results and many literature results. It is also shown how the UOC approach allows the probing of temperatures that cross through the crystalline melting point region of semi-crystalline materials such as XLPO and EPR cable insulations. New results on combined environment aging of neoprene and hypalon cable jacketing materials are presented and offer additional evidence in support of our time-temperature-dose rate (t-T-DR) superposition approach that had been used successfully in the past for such situations.

Assink, Roger Alan; Gillen, Kenneth Todd; Bernstein, Robert

2005-11-01T23:59:59.000Z

277

A Novel Approach to Material Development for Advanced Reactor Systems. Quarterly progress report, Year 1 - Quarter 2  

SciTech Connect (OSTI)

OAK B188 A Novel Approach to Material Development for Advanced Reactor Systems. Quarterly progress report, Year 1--Quarter 2. Year one of this project had three major goals. First, to specify, order and install a new high current ion source for more rapid and stable proton irradiation. Second, to assess the use low temperature irradiation and chromium pre-enrichment in an effort to isolate a radiation damage microstructure in stainless steels without the effects of RIS. Third, to prepare for the irradiation of reactor pressure vessel steel and Zircaloy. Program goals for Second Quarter, Year One: In year 1 quarter 2, the project goal was to complete an irradiation of an RPV steel sample and begin sample characterization. We also planned to identify sources of Zircaloy for irradiation and characterization.

None

2000-03-27T23:59:59.000Z

278

Large area nuclear particle detectors using ET materials, phase 2. Final report, 9 May 1988-9 May 1990  

SciTech Connect (OSTI)

This report presents work done under a Phase 2 SBIR contract for demonstrating large area detector planes utilizing Quantex electron trapping materials as a film medium for storing high-energy nuclide impingement information. The detector planes utilize energy dissipated by passage of the high-energy nuclides to produce localized populations of electrons stored in traps. Readout of the localized trapped electron populations is effected by scanning the ET plane with near-infrared, which frees the trapped electrons and results in optical emission at visible wavelengths. The effort involved both optimizing fabrication technology for the detector planes and developing a readout system capable of high spatial resolution for displaying the recorded nuclide passage tracks.

Wrigley, C.Y.; Storti, G.M.; Walter, L.; Mathews, S.

1990-05-01T23:59:59.000Z

279

Report on the joint meeting of the Division of Development and Technology Plasma/Wall Interaction and High Heat Flux Materials and Components Task Groups  

SciTech Connect (OSTI)

This report of the Joint Meeting of the Division of Development and Technology Plasma/Wall Interaction and High Heat Flux Materials and Components Task Groups contains contributing papers in the following areas: Plasma/Materials Interaction Program and Technical Assessment, High Heat Flux Materials and Components Program and Technical Assessment, Pumped Limiters, Ignition Devices, Program Planning Activities, Compact High Power Density Reactor Requirements, Steady State Tokamaks, and Tritium Plasma Experiments. All these areas involve the consideration of High Heat Flux on Materials and the Interaction of the Plasma with the First Wall. Many of the Test Facilities are described as well. (LSP)

Wilson, K.L. (ed.)

1985-10-01T23:59:59.000Z

280

Milestone Report - Complete New Adsorbent Materials for Marine Testing to Demonstrate 4.5 g-U/kg Adsorbent  

SciTech Connect (OSTI)

This report describes work on the successful completion of Milestone M2FT-14OR03100115 (8/20/2014) entitled, Complete new adsorbent materials for marine testing to demonstrate 4.5 g-U/kg adsorbent. This effort is part of the Seawater Uranium Recovery Program, sponsored by the U.S. Department of Energy, Office of Nuclear Energy, and involved the development of new adsorbent materials at the Oak Ridge National Laboratory (ORNL) and marine testing at the Pacific Northwest National Laboratory (PNNL). ORNL has recently developed two new families of fiber adsorbents that have demonstrated uranium adsorption capacities greater than 4.5 g-U/kg adsorbent after marine testing at PNNL. One adsorbent was synthesized by radiation-induced graft polymerization of itaconic acid and acrylonitrile onto high surface area polyethylene fibers followed by amidoximation and base conditioning. This fiber showed a capacity of 4.6 g-U/kg adsorbent in marine testing at PNNL. The second adsorbent was prepared by atom-transfer radical polymerization of t-butyl acrylate and acrylonitrile onto halide-functionalized round fibers followed by amidoximation and base hydrolysis. This fiber demonstrated uranium adsorption capacity of 5.4 g-U/kg adsorbent in marine testing at PNNL.

Janke, Christopher James [ORNL; Das, Sadananda [ORNL; Oyola, Yatsandra [ORNL; Mayes, Richard T. [ORNL; Saito, Tomonori [ORNL; Brown, Suree [ORNL; Gill, Gary [PNNL; Kuo, Li-Jung [PNNL; Wood, Jordana [PNNL

2014-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "materials clsm reported" 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

Hazardous materials in aquatic environments of the Mississippi River Basin. Annual technical report, December 30, 1992--December 29, 1993  

SciTech Connect (OSTI)

Tulane and Xavier Universities have singled out the environment as a major strategic focus for research and training for now and by the year 2000. In December, 1992, the Tulane/Xavier CBR was awarded a five year grant to study pollution in the Mississippi River system. The ``Hazardous Materials in Aquatic Environments of the Mississippi River Basin`` project is a broad research and education program aimed at elucidating the nature and magnitude of toxic materials that contaminate aquatic environments of the Mississippi River Basin. Studies include defining the complex interactions that occur during the transport of contaminants, the actual and potential impact on ecological systems and health, and the mechanisms through which these impacts might be remediated. The Mississippi River Basin represents a model system for analyzing and solving contamination problems that are found in aquatic systems world-wide. These research and education projects are particularly relevant to the US Department of Energy`s programs aimed at addressing aquatic pollution problems associated with DOE National Laboratories. First year funding supported seven collaborative cluster projects and twelve initiation projects. This report summarizes research results for period December 1992--December 1993.

Not Available

1993-12-31T23:59:59.000Z

282

Process research on Semix Silicon Material (PROSSM). Quarterly report No. 5, December 1, 1981-February 28, 1982  

SciTech Connect (OSTI)

Emphasis was shifted from the development of a cost-effective process sequence to research designed to understand the mechanisms of photovoltaic conversion in semicrystalline silicon. With this change has gone a change of title from Module Experimental Process System Development Unit (MEPSDU) to Process Research of Semix Silicon Material (PROSSM). Efforts are now underway to prepare a revised program plan with emphasis on determining the mechanisms limiting voltage and current collection in the semicrystalline silicon. The efforts reported concern work done before the change in emphasis and so the continued development of the cost-effective process sequence is reported. A cost-effective process sequence was identified, equipment was designed to implement a 6.6 MW per year automated production line, and a cost analysis projected a $0.56 per watt cell add-on cost for this line. Four process steps were developed for this program: glass bead back clean-up; hot spray antireflective coating; wave-soldering of fronts; ion milling for edging. While spray dopants were advertised as an off the shelf developed product, they proved to be unreliable with shorter than advertised shelf life. Equipment for handling and processing solar cells is available for all of the cell processing steps identified in this program. During this quarter efforts included work on spray dopant, edging, AR coating, wave soldering and fluxing, ion milling and cost analysis.

Wohlgemuth, J H; Warfield, D B

1982-01-01T23:59:59.000Z

283

MATERIAL BALANCE REPORT  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustion | Department of Energy Low-Temperature Combustion DemonstratorEastLynnF 742 (08-98)

284

Ceramics Technology Project database: September 1991 summary report. [Materials for piston ring-cylinder liner for advanced heat/diesel engines  

SciTech Connect (OSTI)

The piston ring-cylinder liner area of the internal combustion engine must withstand very-high-temperature gradients, highly-corrosive environments, and constant friction. Improving the efficiency in the engine requires ring and cylinder liner materials that can survive this abusive environment and lubricants that resist decomposition at elevated temperatures. Wear and friction tests have been done on many material combinations in environments similar to actual use to find the right materials for the situation. This report covers tribology information produced from 1986 through July 1991 by Battelle columbus Laboratories, Caterpillar Inc., and Cummins Engine Company, Inc. for the Ceramic Technology Project (CTP). All data in this report were taken from the project's semiannual and bimonthly progress reports and cover base materials, coatings, and lubricants. The data, including test rig descriptions and material characterizations, are stored in the CTP database and are available to all project participants on request. Objective of this report is to make available the test results from these studies, but not to draw conclusions from these data.

Keyes, B.L.P.

1992-06-01T23:59:59.000Z

285

LIFE Materials: Topical Assessment Report for LIFE Volume 1 TOPIC: Solid First Wall and Structural Components TASK: Radiation Effects on First Wall  

SciTech Connect (OSTI)

This report consists of the following chapters: CHAPTER A: LIFE Requirements for Materials. Part 1: The structure of the First Wall--Basic requirements; A qualitative view of the challenge; The candidate materials; and Base-line material's properties. CHAPTER B: Summary of Existing Knowledge--Brief historical introduction; Design window; The temperature window; Evolution of the design window with damage; Damage calculations; He and H production; Swelling resistance; Incubation dose for swelling; Design criterion No. 1, Strength; Design criterion No. 2, Corrosion resistance; Design criterion No. 3, Creep resistance; Design criterion No. 4, Radiation induced embrittlement; and Conclusions. CHAPTER C: Identification of Gaps in Knowledge & Vulnerabilities. CHAPTER D: Strategy and Future Work.

Caro, A

2008-11-26T23:59:59.000Z

286

Evaluation of dry-solids-blend material source for grouts containing 106-AN waste: September 1990 progress report  

SciTech Connect (OSTI)

Stabilization/solidification (S/S) is the most widely used technology for the treatment and ultimate disposal of both radioactive and chemically hazardous wastes. Such technology is being utilized in a Grout Treatment Facility (GTF) by the Westinghouse Hanford Company (WHC) for the disposal of various wastes, including 106-AN wastes, located on the Hanford Reservation. The WHC personnel have developed a grout formula for 106-AN disposal that is designed to meet stringent performance requirements. This formula consists of a dry-solids blend containing 40 wt % limestone, 28 wt % granulated blast furnace slag (BFS), 28 wt % ASTM Class F fly ash, and 4 wt % Type I-II-LA Portland cement. The blend is mixed with 106-AN waste at a ratio of 9 lb of dry-solids blend per gallon of waste. This report documents progress made to date on efforts at Oak Ridge National Laboratory (ORNL) in support of WHC`s Grout Technology Program to assess the effects of the source of the dry-solids-blend materials on the resulting grout formula.

Gilliam, T.M.; Osborne, S.C.; Francis, C.L.; Scott, T.C.

1993-09-01T23:59:59.000Z

287

End State Condition Report for Materials and Fuels Complex Facilities MFC-799, 799A, and 770C  

SciTech Connect (OSTI)

The Materials and Fuels Complex (MFC) facilities MFC-799, Sodium Processing Facility (a single building consisting of two areas: the Sodium Process Area and the Carbonate Process Area); MFC-799A, Caustic Storage Area; and MFC-770C, Nuclear Calibration Laboratory, have been declared excess to future Department of Energy (DOE) Office of Nuclear Energy(NE) mission requirements. Transfer of these facilities from NE to the DOE Office of Environmental Management (EM), and an associated schedule for doing so, have been agreed upon by the two offices. This report documents the completion of pre-transfer stabilization actions, as identified in DOE Guide 430.1-5, Transition Implementation Guide, for buildings MFC-799/799A and 770C, and indicates that these facilities are ready for transfer from NE to EM. The facilities are in a known, safe condition and information is provided to support efficient decommissioning and demolition (D&D) planning while minimizing the possibility of encountering unforeseen circumstances during the D&D activities.

Gary Mecham

2010-10-01T23:59:59.000Z

288

Reports  

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

Reports Reports Individual Permit reports are prepared annually to facilitate public review of activities for the previous year. Contact Environmental Communication & Public...

289

STATUS REPORT FOR AGING STUDIES OF EPDM O-RING MATERIAL FOR THE H1616 SHIPPING PACKAGE  

SciTech Connect (OSTI)

This is an interim status report for tasks carried out per Task Technical Plan SRNL-STI-2011-00506. A series of tasks/experiments are being performed at the Savannah River National Laboratory to monitor the aging performance of ethylene propylene diene monomer (EPDM) Orings used in the H1616 shipping package. The data will support the technical basis to extend the annual maintenance of the EPDM O-rings in the H1616 shipping package and to predict the life of the seals at bounding service conditions. Current expectations are that the O-rings will maintain a seal at bounding normal temperatures in service (152 F) for at least 12 months. The baseline aging data review suggests that the EPDM O-rings are likely to retain significant mechanical properties and sealing force at bounding service temperatures to provide a service life of at least 2 years. At lower, more realistic temperatures, longer service life is likely. Parallel compression stress relaxation and vessel leak test efforts are in progress to further validate this assessment and quantify a more realistic service life prediction. The H1616 shipping package O-rings were evaluated for baseline property data as part of this test program. This was done to provide a basis for comparison of changes in material properties and performance parameters as a function of aging. This initial characterization was limited to physical and mechanical properties, namely hardness, thickness and tensile strength. These properties appear to be consistent with O-ring specifications. Three H1616-1 Containment Vessels were placed in test conditions and are aging at temperatures ranging from 160 to 300 F. The vessels were Helium leak-tested initially and have been tested at periodic intervals after cooling to room temperature to determine if they meet the criterion of leaktightness defined in ANSI standard N14.5-97 (< 1E-07 std cc air/sec at room temperature). To date, no leak test failures have occurred. The cumulative time at temperature ranges from 174 days for the 300 F vessel to 189 days for the 160 F vessel as of 8/1/2012. The compression stress-relaxation (CSR) behavior of H1616 shipping package O-rings is being evaluated to develop an aging model based on material properties. O-ring segments were initially aged at four temperatures (175 F, 235 F, 300 F and 350 F). These temperatures were selected to bound normal service temperatures and to challenge the seals within a reasonable aging period. Currently, samples aging at 300 F and 350 F have reached the mechanical failure point (end of life) which is defined in this study as 90% loss of initial sealing force. As a result, additional samples more recently began aging at {approx}270 F to provide additional data for the aging model. Aging and periodic leak testing of the full containment vessels, as well as CSR testing of O-ring segments is ongoing. Continued testing per the Task Technical Plan is recommended in order to validate the assumptions outlined in this status report and to quantify and validate the long-term performance of O-ring seals under actual service conditions.

Stefek, T.; Daugherty, W.; Skidmore, E.

2012-08-31T23:59:59.000Z

290

NEXT GENERATION SOLVENT-MATERIALS COMPATIBILITY WITH POLYMER COMPONENTS WITHIN MODULAR CAUSTIC-SIDE SOLVENT EXTRACTION UNIT (FINAL REPORT)  

SciTech Connect (OSTI)

The Office of Waste Processing, within the Office of Technology Innovation and Development, is funding the development of an enhanced solvent for deployment at the Savannah River Site for removal of cesium from High Level Waste. The technical effort is collaboration between Oak Ridge National Laboratory (ORNL), Savannah River National Laboratory (SRNL), and Argonne National Laboratory. The first deployment target for the technology is within the Modular Caustic-Side Solvent Extraction Unit (MCU). Deployment of a new chemical within an existing facility requires verification that the chemical components are compatible with the installed equipment. In the instance of a new organic solvent, the primary focus is on compatibility of the solvent with organic polymers used in the facility. This report provides the data from exposing these polymers to the Next Generation Solvent (NGS). The test was conducted over six months. An assessment of the dimensional stability of polymers present in MCU (i.e., PEEK, Grafoil, Tefzel and Isolast) in the modified NGS (where the concentration of LIX{reg_sign}79 and MaxCalix was varied systematically) showed that LIX{reg_sign}79 selectively affected Tefzel and its different grades (by an increase in size and lowering its density). The copolymer structure of Tefzel and possibly its porosity allows for the easier diffusion of LIX{reg_sign}79. Tefzel is used as the seat material in some of the valves at MCU. Long term exposure to LIX{reg_sign}79, may make the valves hard to operate over time due to the seat material (Tefzel) increasing in size. However, since the physical changes of Tefzel in the improved solvent are comparable to the changes in the CSSX baseline solvent, no design changes are needed with respect to the Tefzel seating material. PEEK, Grafoil and Isolast were not affected by LIX{reg_sign}79 and MaxCalix within six months of exposure. The initial rapid weight gain observed in every polymer is assigned to the finite and limited uptake of Isopar{reg_sign} L/Modifier by the polymers probably due to the polymers porosity and rough surfaces. Spectroscopic data on the organic liquid and the polymer surfaces showed no preferential adsorption of any component in the NGS to the polymers and with the exception of CPVC, no leachate was observed in the NGS from any of the polymers studied. The testing shows no major concerns for compatibility over the short duration of these tests but does indicate that longer duration exposure studies are warranted, especially for Tefzel. However, the physical changes experienced by Tefzel in the improved solvent were comparable to the physical changes obtained when Tefzel is placed in CSSX baseline solvent. Therefore, there is no effect of the improved solvent beyond those observed in CSSX baseline solvent.

Fondeur, F.; Peters, T.; Fink, S.

2012-01-17T23:59:59.000Z

291

Safety analysis report for the use of hazardous production materials in photovoltaic applications at the National Renewable Energy Laboratory  

SciTech Connect (OSTI)

To ensure the continued safety of SERI's employees, the community, and the environment, NREL commissioned an internal audit of its photovoltaic operations that used hazardous production materials (HPMS). As a result of this audit, NREL management voluntarily suspended all operations using toxic and/or pyrophoric gases. This suspension affected seven laboratories and ten individual deposition systems. These activities are located in Building 16, which has a permitted occupancy of Group B, Division 2 (B-2). NREL management decided to do the following. (1) Exclude from this SAR all operations which conformed, or could easily be made to conform, to B-2 Occupancy requirements. (2) Include in this SAR all operations that could be made to conform to B-2 Occupancy requirements with special administrative and engineering controls. (3) Move all operations that could not practically be made to conform to B-2 occupancy requirements to alternate locations. In addition to the layered set of administrative and engineering controls set forth in this SAR, a semiquantitative risk analysis was performed on 30 various accident scenarios. Twelve presented only routine risks, while 18 presented low risks. Considering the demonstrated safe operating history of NREL in general and these systems specifically, the nature of the risks identified, and the layered set of administrative and engineering controls, it is clear that this facility falls within the DOE Low Hazard Class. Each operation can restart only after it has passed an Operational Readiness Review, comparing it to the requirements of this SAR, while subsequent safety inspections will ensure future compliance. This document contains the appendices to the NREL safety analysis report.

Crandall, R.S.; Nelson, B.P.; Moskowitz, P.D.; Fthenakis, V.M.

1992-07-01T23:59:59.000Z

292

Fossil Energy Advanced Research and Technology Development Materials Program. Semiannual progress report for the period ending September 30, 1992  

SciTech Connect (OSTI)

Objective of this materials program is to conduct R and D on materials for fossil energy applications with focus on longer-term and generic needs of the various fossil fuel technologies. The projects are organized according to materials research areas: (1) ceramics, (2) new alloys: iron aluminides, advanced austenitics and chromium niobium alloys, and (3) technology development and transfer. Separate abstracts have been prepared.

Cole, N.C.; Judkins, R.R. [comps.

1992-12-01T23:59:59.000Z

293

Evaluation of improved materials for stationary diesel engines operating on residual and coal based fuels. Final report  

SciTech Connect (OSTI)

Experimental results to date from an on-going research program on improved materials for stationary diesel engines using residual or coal-based fuels are presented with little discussion of conclusions about these results. Information is included on ring and liner wear, fuel oil qualities, ceramic materials, coatings, test procedures and equipment, and tribology test results. (LCL)

Not Available

1980-01-01T23:59:59.000Z

294

Hazardous materials in aquatic environments of the Mississippi River Basin. Quarterly progress report, July 1, 1995--September 30, 1995  

SciTech Connect (OSTI)

This report is the quarterly progress report for July through September 1995 for work done by Tulane and Xavier Universities under DOE contract number DE-FG01-93-EW53023. Accomplishments for various tasks including administrative activities, collaborative cluster projects, education projects, initiation projects, coordinated instrumentation facility, and an investigators` retreat are detailed in the report.

NONE

1995-12-01T23:59:59.000Z

295

Dynamic Processes in Biology, Chemistry, and Materials Science: Opportunities for UltraFast Transmission Electron Microscopy - Workshop Summary Report  

SciTech Connect (OSTI)

This report summarizes a 2011 workshop that addressed the potential role of rapid, time-resolved electron microscopy measurements in accelerating the solution of important scientific and technical problems. A series of U.S. Department of Energy (DOE) and National Academy of Science workshops have highlighted the critical role advanced research tools play in addressing scientific challenges relevant to biology, sustainable energy, and technologies that will fuel economic development without degrading our environment. Among the specific capability needs for advancing science and technology are tools that extract more detailed information in realistic environments (in situ or operando) at extreme conditions (pressure and temperature) and as a function of time (dynamic and time-dependent). One of the DOE workshops, Future Science Needs and Opportunities for Electron Scattering: Next Generation Instrumentation and Beyond, specifically addressed the importance of electron-based characterization methods for a wide range of energy-relevant Grand Scientific Challenges. Boosted by the electron optical advancement in the last decade, a diversity of in situ capabilities already is available in many laboratories. The obvious remaining major capability gap in electron microscopy is in the ability to make these direct in situ observations over a broad spectrum of fast (s) to ultrafast (picosecond [ps] and faster) temporal regimes. In an effort to address current capability gaps, EMSL, the Environmental Molecular Sciences Laboratory, organized an Ultrafast Electron Microscopy Workshop, held June 14-15, 2011, with the primary goal to identify the scientific needs that could be met by creating a facility capable of a strongly improved time resolution with integrated in situ capabilities. The workshop brought together more than 40 leading scientists involved in applying and/or advancing electron microscopy to address important scientific problems of relevance to DOEs research mission. This workshop built on previous workshops and included three breakout sessions identifying scientific challenges in biology, biogeochemistry, catalysis, and materials science frontier areas of fundamental science that underpin energy and environmental science that would significantly benefit from ultrafast transmission electron microscopy (UTEM). In addition, the current status of time-resolved electron microscopy was examined, and the technologies that will enable future advances in spatio-temporal resolution were identified in a fourth breakout session.

Kabius, Bernd C.; Browning, Nigel D.; Thevuthasan, Suntharampillai; Diehl, Barbara L.; Stach, Eric A.

2012-07-25T23:59:59.000Z

296

Fiscal year 1997 final report for task plan SR-16WT-31 task B, vitrification of ion exchange material  

SciTech Connect (OSTI)

In Fiscal Year 1997, the Department of Energy Tanks Focus Area (TFA) funded the Savannah River Technology Center (SRTC) to develop and demonstrate the vitrification of a CST ion exchange material loaded with radioactive cesium from one of the Melton Valley Storage Tanks at the Oak Ridge National Laboratory (ORNL). SRTC developed a patent-pending glass formulation that can be used to vitrify CST sorbent producing a quality borosilicate glass waste form. SRTC demonstrated this formulation by vitrifying the radioactive CST in the SRTC shielded cells melter.In addition to the formulation developed for vitrification of the `CST-only` glass waste form, SRTC also developed formulations for vitrification of CST coupled with High-Level Waste (HLW) sludges. A Defense Waste Processing Facility (DWPF) coupled feed formulation has been developed with up to 10 weight percent CST and 28 weight percent DWPF sludge oxides. A coupled Hanford formulation has also been developed for producing quality glass waste forms with up to 10 weight percent CST and 45 weight percent Hanford sludge oxides. The significant accomplishments of this project were then development of CST-only glass formulations incorporating up to 65 weight-percent CST, development of techniques for delivering a slurry or dry feed to a joule-heated melter, demonstration of a CST-only glass formulation in a continuous melter operation, demonstration of compliance with the Nevada Test Site (NTS) Waste Acceptance Criteria (WAC), development of CST-sludge glass formulations incorporating up to 10 weight percent CST and 28 weight percent DWPF sludges oxides, demonstration of CST-sludge glass formulations using radioactive sludge and radioactive CST, development of CST-sludge glass formulations incorporating up to 10 weight percent CST and 45 weight percent. All commitments made to the TFA have been met as indicated by the associated milestones. Milestones and the month in which they were completed: Initiate Immobilization of CST in Glass (completed 8/97); Demonstrate that Sludge-CST Glass Satisfied PC Specs in WAPS (completed 9/97); Determine Process Parameters of Sludge-CST Glass (completed 8/97); Demonstrate that CST-Only Glass Satisfied PC Specs in WAPS (completed 9/97); Determine Process Parameters of CST-Only Glass (completed 9/97). The results for Task B of Task Plan SR-16WT-31 have been documented in reports that have been included as attachments. The following is a summary of the attachments from the CST vitrification project.

Ferrara, D.; Andrews, M.K.; Harbour, J.R.; Fellinger, T.L.; Herman, D.T.; Marshall, K.M.; Workman, P.J.

1997-09-30T23:59:59.000Z

297

Conceptual design report: Nuclear materials storage facility renovation. Part 5, Structural/seismic investigation. Section A report, existing conditions calculations/supporting information  

SciTech Connect (OSTI)

The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. Based upon US Department of Energy (DOE) Albuquerque Operations (DOE/Al) Office and LANL projections, storage space limitations/restrictions will begin to affect LANL`s ability to meet its missions between 1998 and 2002.

NONE

1995-07-14T23:59:59.000Z

298

Heavy vehicle propulsion system materials program semi-annual progress report for October 1997 through March 1998  

SciTech Connect (OSTI)

The purpose of the Heavy Vehicle Propulsion System materials Program is the development of materials: ceramics, intermetallics, metal alloys, and metal and ceramic coatings, to support the dieselization of class 1--3 trucks to realize a 35{percent} fuel-economy improvement over current gasoline-fueled trucks and to support commercialization of fuel-flexible LE-55 low-emissions, high-efficiency diesel engines for class 7--8 trucks. The Office of Transportation Technologies, Office of Heavy Vehicle Technologies (OTT OHVT) has an active program to develop the technology for advanced LE-55 diesel engines with 55{percent} efficiency and low emissions levels of 2.0 g/bhp-h NO{sub x} and 0.05 g/bhp-h particulates. The goal is also for the LE-55 engine to run on natural gas with efficiency approaching that of diesel fuel. The LE-55 program is being completed in FY 1997 and, after approximately 10 years of effort, has largely met the program goals of 55{percent} efficiency and low emissions. However, the commercialization of the LE-55 technology requires more durable materials than those that have been used to demonstrate the goals. Heavy Vehicle Propulsion System Materials will, in concert with the heavy-duty diesel engine companies, develop the durable materials required to commercialize the LE-55 technologies.

Johnson, D.R.

1998-06-01T23:59:59.000Z

299

Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1980-March 31, 1980  

SciTech Connect (OSTI)

Results are presented of work performed on the Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Included are the activities associated with the status of the simulated reactor helium supply system, testing equipment and gas chemistry analysis instrumentation and equipment. The progress in the screening test program is described, including screening creep results and metallographic analysis for materials thermally exposed or tested at 750, 850, and 950/sup 0/C.

Not Available

1980-06-25T23:59:59.000Z

300

Final LDRD report : nanoscale mechanisms in advanced aging of materials during storage of spent %22high burnup%22 nuclear fuel.  

SciTech Connect (OSTI)

We present the results of a three-year LDRD project focused on understanding microstructural evolution and related property changes in Zr-based nuclear cladding materials towards the development of high fidelity predictive simulations for long term dry storage. Experiments and modeling efforts have focused on the effects of hydride formation and accumulation of irradiation defects. Key results include: determination of the influence of composition and defect structures on hydride formation; measurement of the electrochemical property differences between hydride and parent material for understanding and predicting corrosion resistance; in situ environmental transmission electron microscope observation of hydride formation; development of a predictive simulation for mechanical property changes as a function of irradiation dose; novel test method development for microtensile testing of ionirradiated material to simulate the effect of neutron irradiation on mechanical properties; and successful demonstration of an Idaho National Labs-based sample preparation and shipping method for subsequent Sandia-based analysis of post-reactor cladding.

Clark, Blythe G.; Rajasekhara, Shreyas; Enos, David George; Dingreville, Remi Philippe Michel; Doyle, Barney Lee; Hattar, Khalid Mikhiel; Weiner, Ruth F.

2013-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "materials clsm reported" 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

2011 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site's Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond  

SciTech Connect (OSTI)

This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (LA-000160-01), for the wastewater reuse site at the Idaho National Laboratory Site's Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond from November 1, 2010 through October 31, 2011. The report contains the following information: (1) Facility and system description; (2) Permit required effluent monitoring data and loading rates; (3) Groundwater monitoring data; (4) Status of special compliance conditions; and (5) Discussion of the facility's environmental impacts. During the 2011 reporting year, an estimated 6.99 million gallons of wastewater were discharged to the Industrial Waste Ditch and Pond which is well below the permit limit of 13 million gallons per year. Using the dissolved iron data, the concentrations of all permit-required analytes in the samples from the down gradient monitoring wells were below the Ground Water Quality Rule Primary and Secondary Constituent Standards.

David Frederick

2012-02-01T23:59:59.000Z

302

2013 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Sites Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond  

SciTech Connect (OSTI)

This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (WRU-I-0160-01, formerly LA 000160 01), for the wastewater reuse site at the Idaho National Laboratory Sites Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond from November 1, 2012 through October 31, 2013. The report contains the following information: Facility and system description Permit required effluent monitoring data and loading rates Groundwater monitoring data Status of special compliance conditions Discussion of the facilitys environmental impacts During the 2013 reporting year, an estimated 9.64 million gallons of wastewater were discharged to the Industrial Waste Ditch and Pond which is well below the permit limit of 17 million gallons per year. The concentrations of all permit-required analytes in the samples from the down gradient monitoring wells were below the applicable Idaho Department of Environmental Qualitys groundwater quality standard levels.

Mike Lewis

2014-02-01T23:59:59.000Z

303

2012 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Sites Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond  

SciTech Connect (OSTI)

This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (WRU-I-0160-01, formerly LA 000160 01), for the wastewater reuse site at the Idaho National Laboratory Sites Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond from November 1, 2011 through October 31, 2012. The report contains the following information: Facility and system description Permit required effluent monitoring data and loading rates Groundwater monitoring data Status of special compliance conditions Discussion of the facilitys environmental impacts During the 2012 reporting year, an estimated 11.84 million gallons of wastewater were discharged to the Industrial Waste Ditch and Pond which is well below the permit limit of 17 million gallons per year. The concentrations of all permit-required analytes in the samples from the down gradient monitoring wells were below the Ground Water Quality Rule Primary and Secondary Constituent Standards.

Mike Lewis

2013-02-01T23:59:59.000Z

304

2010 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site's Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond  

SciTech Connect (OSTI)

This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (#LA 000160 01), for the wastewater reuse site at the Idaho National Laboratory Sites Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond from May 1, 2010 through October 31, 2010. The report contains the following information: Facility and system description Permit required effluent monitoring data and loading rates Groundwater monitoring data Status of special compliance conditions Discussion of the facilitys environmental impacts During the 2010 partial reporting year, an estimated 3.646 million gallons of wastewater were discharged to the Industrial Waste Ditch and Pond which is well below the permit limit of 13 million gallons per year. The concentrations of all permit-required analytes in the samples from the down gradient monitoring wells were below the Ground Water Quality Rule Primary and Secondary Constituent Standards.

David B. Frederick

2011-02-01T23:59:59.000Z

305

Low-Density and High Porosity Hydrogen Storage Materials Built from Ultra-Light Elements. Final Scientific/Technical Report  

SciTech Connect (OSTI)

A number of significant advances have been achieved, opening up new opportunities for the synthetic development of novel porous materials and their energy-related applications including gas storage and separation and catalysis. These include lithium-based metal-organic frameworks, magnesium-based metal-organic frameworks, and high gas uptake in porous frameworks with high density of open donor sites.

Feng, Pingyun

2014-01-10T23:59:59.000Z

306

Design and fabrication of advanced materials from Illinois coal wastes. [Quarterly] technical report, September 1--November 30, 1994  

SciTech Connect (OSTI)

The main goal of this project is to develop a bench-scale procedure to design and fabricate advanced brake and structural composite materials from Illinois coal combustion residues. During the first quarter of the project, the thrust of the work was directed towards setting up the experimental facilities and undertaking preliminary tests to gauge the ability of coal tar derived binder in fabricating the brake skeletons. In addition systematic scanning electron microscopy (SEM), differential scanning calorimetry (DSC), and differential thermal analysis (DTA) were conducted on PCC fly ash (Baldwin), fly ash (ADM), FBC fly ash, FBC spent bed bottom ash, bottom ash (ADM), and scrubber sludge residues to characterize their geometrical shape and thermal stability. The PCC fly ash particles being highly spherical in shape and thermally inert up to 1100{degrees}C will make an excellent raw material for our composites. This is born out by fabricating brake skeletons from PCC fly ash colloids. Unlike the PCC fly ash and FBC fly ash, the scrubber sludge particles are not suitable hosts for our brake lining materials because of a whisker-like particle structure. Six different compositions of various combustion residues were tested in the fabrication of brake skeletons, and our tar derived binder shows great promise in the fabrication of composite materials.

Malhotra, V.M.; Wright, M.A. [Southern Illinois Univ., Carbondale, IL (United States)

1994-12-31T23:59:59.000Z

307

Roadmapping the Resolution of Gas Generation Issues in Packages Containing Radioactive Waste/Materials - A Status Report  

SciTech Connect (OSTI)

Gas generation issues, particularly hydrogen, have been an area of concern for the transport and storage of radioactive materials and waste in the Department of Energy (DOE) Complex. Potentially combustible gases can be generated through a variety of reactions, including chemical reactions and radiolytic decomposition of hydrogen- containing material. Since transportation regulations prohibit shipment of explosives and radioactive materials together, it was decided that hydrogen generation was a problem that warranted the execution of a high-level roadmapping effort. This paper discusses the major gas generation issues within the DOE Complex and the research that has been and is being conducted by the transuranic (TRU) waste, nuclear materials, and spent nuclear fuels (SNF) programs within DOEs Environmental Management (EM) organizations to address gas generation concerns. This paper presents a "program level" roadmap that links technology development to program needs and identifies the probability of success in an effort to understand the programmatic risk associated with the issue of gas generation. This paper also presents the status of the roadmap and follow-up activities.

Luke, Dale Elden; Hamp, S.

2002-02-01T23:59:59.000Z

308

Roadmapping the Resolution of Gas Generation Issues in Packages Containing Radioactive Waste/Materials - A Status Report  

SciTech Connect (OSTI)

Gas generation issues, particularly hydrogen, have been an area of concern for the transport and storage of radioactive materials and waste in the Department of Energy (DOE) Complex. Potentially combustible gases can be generated through a variety of reactions, including chemical reactions and radiolytic decomposition of hydrogen-containing material. Since transportation regulations prohibit shipment of explosives and radioactive materials together, it was decided that hydrogen generation was a problem that warranted the execution of a high-level roadmapping effort. This paper discusses the major gas generation issues within the DOE Complex and the research that has been and is being conducted by the transuranic (TRU) waste, nuclear materials, and spent nuclear fuels (SNF) programs within DOE's Environmental Management (EM) organizations to address gas generation concerns. This paper presents a ''program level'' roadmap that links technology development to program needs and identifies the probability of success in an effort to understand the programmatic risk associated with the issue of gas generation. This paper also presents the status of the roadmap and follow-up activities.

Luke, D.E. (INEEL); Hamp, S. (DOE-Albuquerque Operations Office)

2002-01-04T23:59:59.000Z

309

Chemical Emissions of Residential Materials and Products: Review of Available Information Improving Ventilation and Saving Energy: Final Report on  

E-Print Network [OSTI]

Chemical Emissions of Residential Materials and Products: Review of Available Information with industry, a prototype improved heat pump air conditioner was developed to meet the specification. A one portable classrooms equipped with standard 10 SEER heat pump air conditioner equipment. The IHPAC units

310

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

311

Porous Materials Porous Materials  

E-Print Network [OSTI]

1 Porous Materials x Porous Materials · Physical properties * Characteristic impedance p = p 0 e -jk xa- = vej[ ] p x - j ; Zc= p ve = c ka 0k = c 1-j #12;2 Porous Materials · Specific acoustic impedance Porous Materials · Finite thickness ­ blocked p e + -jk (x-d)a p e - jk (x-d)a d x #12

Berlin,Technische Universität

312

PISCES Program: Plasma-materials interactions and edge-plasma physics research. Progress report, 1991--1992  

SciTech Connect (OSTI)

This program investigates and characterizes the behavior of materials under plasma bombordment, in divertor regions. The PISCES facility is used to study divertor and plasma edge management concepts (in particular gas target divertors), as well as edge plasma turbulence and transport. The plasma source consists of a hot LaB{sub 6} cathode with an annular, water-cooled anode and attached drift tube. This cross sectional area of the plasma can be adjusted between 3 and 10 cm. A fast scanning diagnostic probe system was used for mapping plasma density profiles during biased limiter and divertor simulation experiments. Some experimental data are given on: (1) materials and surface physics, (2) edge plasma physics, and (3) a theoretical analysis of edge plasma modelling.

Conn, R.W.; Hirooka, Y.

1992-07-01T23:59:59.000Z

313

Annual Technical Progress Report of Radioisotope Power Systems Materials Production and Technology Program Tasks for October 1, 2006 Through September 30, 2007  

SciTech Connect (OSTI)

The Office of Radioisotope Power Systems of the Department of Energy (DOE) provides Radioisotope Power Systems (RPS) for applications where conventional power systems are not feasible. For example, radioisotope thermoelectric generators were supplied by the DOE to the National Aeronautics and Space Administration for deep space missions including the Cassini Mission launched in October of 1997 to study the planet Saturn. For the Cassini Mission, ORNL produced carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, and clad vent sets (CVS) used in the generators. The Oak Ridge National Laboratory (ORNL) has been involved in developing materials and technology and producing components for the DOE for more than three decades. This report reflects program guidance from the Office of Radioisotope Power Systems for fiscal year (FY) 2007. Production activities for prime quality (prime) CBCF insulator sets, iridium alloy blanks and foil, and CVS are summarized in this report. Technology activities are also reported that were conducted to improve the manufacturing processes, characterize materials, or to develop information for new radioisotope power systems.

King, James F [ORNL

2008-04-01T23:59:59.000Z

314

ANNUAL TECHNICAL PROGRESS REPORT OF RADIOISOTOPE POWER SYSTEM MATERIALS PRODUCTION AND TECHNOLOGY PROGRAM TASKS FOR OCTOBER 1, 2005 THROUGH SEPTEMBER 30, 2006  

SciTech Connect (OSTI)

The Office of Space and Defense Power Systems of the Department of Energy (DOE) provides Radioisotope Power Systems (RPS) for applications where conventional power systems are not feasible. For example, radioisotope thermoelectric generators were supplied by the DOE to the National Aeronautics and Space Administration for deep space missions including the Cassini Mission launched in October of 1997 to study the planet Saturn. For the Cassini Mission, ORNL produced carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, and clad vent sets (CVS) used in the generators. The Oak Ridge National Laboratory (ORNL) has been involved in developing materials and technology and producing components for the DOE for more than three decades. This report reflects program guidance from the Office of Space and Defense Power Systems for fiscal year (FY) 2006. Production activities for prime quality (prime) CBCF insulator sets, iridium alloy blanks and foil, and CVS are summarized in this report. Technology activities are also reported that were conducted to improve the manufacturing processes, characterize materials, or to develop information for new radioisotope power systems.

King, James F [ORNL

2007-04-01T23:59:59.000Z

315

Annual Technical Progress Report of Radioisotope Power Systems Materials Production and Technology Program Tasks for October 1, 2007 Through September 30,2008  

SciTech Connect (OSTI)

The Office of Radioisotope Power Systems (RPS) of the Department of Energy (DOE) provides RPS for applications where conventional power systems are not feasible. For example, radioisotope thermoelectric generators were supplied by the DOE to the National Aeronautics and Space Administration (NASA) for deep space missions including the Cassini Mission launched in October of 1997 to study the planet Saturn. For the Cassini Mission, ORNL produced carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, and clad vent sets (CVS) used in the generators. The Oak Ridge National Laboratory (ORNL) has been involved in developing materials and technology and producing components for the DOE for more than three decades. This report reflects program guidance from the Office of RPS for fiscal year (FY) 2008. Production activities for prime quality (prime) CBCF insulator sets, iridium alloy blanks and foil, and CVS are summarized in this report. Technology activities are also reported that were conducted to improve the manufacturing processes, characterize materials, or to develop information for new RPS.

King, James F [ORNL

2009-04-01T23:59:59.000Z

316

Annual Technical Progress Report of Radioisotope Power System Materials Production and Technical Program Tasks for October 1, 2005 through September 30, 2006  

SciTech Connect (OSTI)

The Office of Space and Defense Power Systems of the Department of Energy (DOE) provides Radioisotope Power Systems (RPS) for applications where conventional power systems are not feasible. For example, radioisotope thermoelectric generators were supplied by the DOE to the National Aeronautics and Space Administration for deep space missions including the Cassini Mission launched in October of 1997 to study the planet Saturn. For the Cassini Mission, ORNL produced carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, and clad vent sets (CVS) used in the generators. The Oak Ridge National Laboratory (ORNL) has been involved in developing materials and technology and producing components for the DOE for more than three decades. This report reflects program guidance from the Office of Space and Defense Power Systems for fiscal year (FY) 2006. Production activities for prime quality (prime) CBCF insulator sets, iridium alloy blanks and foil, and CVS are summarized in this report. Technology activities are also reported that were conducted to improve the manufacturing processes, characterize materials, or to develop information for new radioisotope power systems.

None

2007-04-02T23:59:59.000Z

317

ANNUAL TECHNICAL PROGRESS REPORT OF RADIOISOTOPE POWER SYSTEMS MATERIALS PRODUCTION AND TECHNOLOGY PROGRAM TASKS FOR OCTOBER 1, 2010 THROUGH SEPTEMBER 30, 2011  

SciTech Connect (OSTI)

The Office of Space and Defense Power Systems of the Department of Energy (DOE) provides Radioisotope Power Systems (RPS) for applications where conventional power systems are not feasible. For example, radioisotope thermoelectric generators were supplied by the DOE to the National Aeronautics and Space Administration (NASA) for deep space missions including the Cassini Mission launched in October of 1997 to study the planet Saturn. For the Cassini Mission, the Oak Ridge National Laboratory (ORNL) produced carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, and clad vent sets (CVS) used in the generators. These components were also produced for the Pluto New Horizons and Mars Science Lab missions launched in January 2006 and November 2011respectively. The ORNL has been involved in developing materials and technology and producing components for the DOE for nearly four decades. This report reflects program guidance from the Office of RPS for fiscal year (FY) 2011. Production activities for prime quality (prime) CBCF insulator sets, iridium alloy blanks and foil, and CVS are summarized in this report. Technology activities are also reported that were conducted to improve the manufacturing processes, characterize materials, or to develop information for new RPS. Work has also been initiated to establish fabrication capabilities for the Light Weight Radioisotope Heater Units.

King, James F [ORNL

2012-05-01T23:59:59.000Z

318

Annual Technical Progress Report of Radioisotope Power System Materials Production and Technology Tasks for October 1, 2004 through September 30, 2005  

SciTech Connect (OSTI)

The Office of Space and Defense Power Systems of the Department of Energy (DOE) provides Radioisotope Power Systems (RPS) for applications where conventional power systems are not feasible. For example, radioisotope thermoelectric generators were supplied by the DOE to the National Aeronautics and Space Administration for deep space missions including the Cassini Mission launched in October of 1997 to study the planet Saturn. For the Cassini Mission, ORNL produced carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, and clad vent sets (CVS) used in the generators. The Oak Ridge National Laboratory (ORNL) has been involved in developing materials and technology and producing components for the DOE for more than three decades. This report reflects program guidance from the Office of Space and Defense Power Systems for fiscal year (FY) 2005. Production activities for prime quality (prime) CBCF insulator sets, iridium alloy blanks and foil, and CVS are summarized in this report. Technology activities are also reported that were conducted to improve the manufacturing processes, characterize materials, or to develop information for new radioisotope power systems.

None listed

2006-08-03T23:59:59.000Z

319

Annual Technical Progress Report of Radioisotope Power System Materials Production and Technology Tasks for October 1, 2003 through September 30, 2004  

SciTech Connect (OSTI)

The Office of Space and Defense Power Systems of the Department of Energy (DOE) provides Radioisotope Power Systems (RPS) for applications where conventional power systems are not feasible. For example, radioisotope thermoelectric generators were supplied by the DOE to the National Aeronautics and Space Administration for deep space missions including the Cassini Mission launched in October of 1997 to study the planet Saturn. For the Cassini Mission, ORNL produced carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, and clad vent sets (CVS) used in the generators. The Oak Ridge National Laboratory (ORNL) has been involved in developing materials and technology and producing components for the DOE for more than three decades. This report reflects program guidance from the Office of Space and Defense Power Systems for fiscal year (FY) 2004. Production and production maintenance activities for flight quality (FQ) CBCF insulator sets, iridium alloy blanks and foil, and CVS are summarized in this report. In all three cases, production maintenance is assured by the manufacture of limited quantities of FQ components. Technology activities are also reported that were conducted to improve the manufacturing processes, characterize materials, or to develop information for new radioisotope power systems.

None listed

2005-06-01T23:59:59.000Z

320

Annual Technical Progress Report of Radioisotope Power System Materials Production and Technology Program Tasks for October 1, 2004 Through September 30, 2005  

SciTech Connect (OSTI)

The Office of Space and Defense Power Systems of the Department of Energy (DOE) provides Radioisotope Power Systems (RPS) for applications where conventional power systems are not feasible. For example, radioisotope thermoelectric generators were supplied by the DOE to the National Aeronautics and Space Administration for deep space missions including the Cassini Mission launched in October of 1997 to study the planet Saturn. For the Cassini Mission, ORNL produced carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, and clad vent sets (CVS) used in the generators. The Oak Ridge National Laboratory (ORNL) has been involved in developing materials and technology and producing components for the DOE for more than three decades. This report reflects program guidance from the Office of Space and Defense Power Systems for fiscal year (FY) 2005. Production activities for prime quality (prime) CBCF insulator sets, iridium alloy blanks and foil, and CVS are summarized in this report. Technology activities are also reported that were conducted to improve the manufacturing processes, characterize materials, or to develop information for new radioisotope power systems.

King, James F [ORNL

2006-06-01T23:59:59.000Z

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


321

Hazardous materials in aquatic environment of the Mississippi River basin. Quarterly progress report, July 1--September 30, 1996  

SciTech Connect (OSTI)

This report is divided into four aspects relating to water pollution problems in the Mississippi River Basin. They are: collaborative cluster research projects, in which investigators employ a synergistic approach to the solution of problems; initiation research projects, in which a single investigator is involved ; technical support activities, which involve anything that is required to support the research; and the research training and education core, which is designed to develop courses with emphasis on environmental studies. This report presents the objectives and accomplishments of the various research projects for July 1, 1996--September 30, 1996.

NONE

1996-12-31T23:59:59.000Z

322

Iron-Based Amorphous-Metals: High-Performance Corrosion-Resistant Materials (HPCRM) Development Final Report  

SciTech Connect (OSTI)

An overview of the High-Performance Corrosion-Resistant Materials (HPCRM) Program, which was co-sponsored by the Defense Advanced Research Projects Agency (DARPA) Defense Sciences Office (DSO) and the United States Department of Energy (DOE) Office of Civilian and Radioactive Waste Management (OCRWM), is discussed. Programmatic investigations have included a broad range of topics: alloy design and composition; materials synthesis; thermal stability; corrosion resistance; environmental cracking; mechanical properties; damage tolerance; radiation effects; and important potential applications. Amorphous alloys identified as SAM2X5 (Fe{sub 49.7}Cr{sub 17.7}Mn{sub 1.9}Mo{sub 7.4}W{sub 1.6}B{sub 15.2}C{sub 3.8}Si{sub 2.4}) and SAM1651 (Fe{sub 48}Mo{sub 14}Cr{sub 15}Y{sub 2}C{sub 15}B{sub 6}) have been produced as melt-spun ribbons, drop-cast ingots and thermal-spray coatings. Chromium (Cr), molybdenum (Mo) and tungsten (W) additions provided corrosion resistance, while boron (B) enabled glass formation. Earlier electrochemical studies of melt-spun ribbons and ingots of these amorphous alloys demonstrated outstanding passive film stability. More recently thermal-spray coatings of these amorphous alloys have been made and subjected to long-term salt-fog and immersion tests. Good corrosion resistance has been observed during salt-fog testing. Corrosion rates were measured in situ with linear polarization, while simultaneously monitoring the open-circuit corrosion potentials. Reasonably good performance was observed. The sensitivity of these measurements to electrolyte composition and temperature was determined. The high boron content of this particular amorphous metal make this amorphous alloy an effective neutron absorber, and suitable for criticality control applications. In general, the corrosion resistance of these iron-based amorphous metals is maintained at operating temperatures up to the glass transition temperature. These materials are much harder than conventional stainless steel and nickel-based materials, and are proving to have excellent wear properties, sufficient to warrant their use in earth excavation, drilling and tunnel boring applications. The observed corrosion resistance may enable applications of importance in industries such as: oil and gas production, refining, nuclear power generation, shipping, and others. Large areas have been successfully coated with these materials, with thicknesses of approximately one centimeter.

Farmer, J C; Choi, J; Saw, C; Haslem, J; Day, D; Hailey, P; Lian, T; Rebak, R; Perepezko, J; Payer, J; Branagan, D; Beardsley, B; D'Amato, A; Aprigliano, L

2009-03-16T23:59:59.000Z

323

Materials Science and Technology Division light-water-reactor safety research program: quarterly progress report, January-March 1983  

SciTech Connect (OSTI)

This progress report summarizes the Argonne National Laboratory work performed during January, February and March 1983 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors, Transient Fuel Response and Fission Product Release, Clad Properties for Code Verification, and Long-Term Embrittlement of Cast Duplex Stainless Steels in LWR Systems.

Not Available

1984-04-01T23:59:59.000Z

324

Materials Science Division light-water-reactor safety-research program. Quarterly progress report, April-June 1982. Volume 2  

SciTech Connect (OSTI)

This progress report summarizes the Argonne National Laboratory work performed during April, May, and June 1982 on water-reactor-safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors, Transient Fuel Response and Fission Product Release, and Clad Properties for Code Verification.

Shack, W.J.; Rest, J.; Kassner, T.F.; Chung, H.M.; Claytor, T.N.; Kupperman, D.S.; Maiya, P.S.; Nichols, F.A.; Park, J.Y.; Ruther, W.E.; Yaggee, F.L.

1983-05-01T23:59:59.000Z

325

Materials Science Division light-water-reactor safety research program. Quarterly progress report, July-September 1982  

SciTech Connect (OSTI)

This progress report summarizes the Argonne National Laboratory work performed during July, August, and September 1982 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors, Transient Fuel Response and Fission Product Release, Clad Properties for Code Verification, Posttest Fuel Examination of the ORNL Fission Product Release Tests, and Examination of TMI-2 Fuel Specimens.

Shack, W.J.; Rest, J.; Kassner, T.F.; Neimark, L.A.; Chung, H.M.; Claytor, T.N.; Kupperman, D.S.; Maiya, P.S.; Nichols, F.A.; Park, J.Y.

1983-08-01T23:59:59.000Z

326

Progress report on the results of testing advanced conceptual design metal barrier materials under relevant environmental conditions for a tuff repository  

SciTech Connect (OSTI)

This report discusses the performance of candidate metallic materials envisioned for fabricating waste package containers for long-term disposal at a possible geological repository at Yucca Mountain, Nevada. Candidate materials include austenitic iron-base to nickel-base alloy (AISI 304L, AISI 316L, and Alloy 825), high-purity copper (CDA 102), and copper-base alloys (CDA 613 and CDA 715). Possible degradation modes affecting these container materials are identified in the context of anticipated environmental conditions at the repository site. Low-temperature oxidation is the dominant degradation mode over most of the time period of concern (minimum of 300 yr to a maximum of 1000 yr after repository closure), but various forms of aqueous corrosion will occur when water infiltrates into the near-package environment. The results of three years of experimental work in different repository-relevant environments are presented. Much of the work was performed in water taken from Well J-13, located near the repository, and some of the experiments included gamma irradiation of the water or vapor environment. The influence of metallurgical effects on the corrosion and oxidation resistance of the material is reviewed; these effects result from container fabrication, welding, and long-term aging at moderately elevated temperatures in the repository. The report indicates the need for mechanisms to understand the physical/chemical reactions that determine the nature and rate of the different degradation modes, and the subsequent need for models based on these mechanisms for projecting the long-term performance of the container from comparatively short-term laboratory data. 91 refs., 17 figs., 16 tabs.

McCright, R.D.; Halsey, W.G.; Van Konynenburg, R.A.

1987-12-01T23:59:59.000Z

327

Detection and Quantitative Analysis of Chemical Species in Hanford Tank Materials Using Raman Spectroscopy Technology: FY94Florida State University Raman Spectroscopy Report  

SciTech Connect (OSTI)

This report provides a summary of work completed in FY-94 by FSU to develop and investigate the feasibility of using Raman spectroscopy with Hanford tank waste materials. Raman performance impacts from sample morphology, including the effects of absorption, particle size, density, color and refractive index, are discussed. An algorithm for relative species concentration measurement from Raman data is presented. An Algorithm for applying Raman to tank waste core screening is presented and discussed. A library of absorption and Raman spectra are presented that support this work.

Reich, F.R.

1997-08-11T23:59:59.000Z

328

Enforcement actions: Significant actions resolved, material licensees. Semiannual progress report, July--December 1997; Volume 16, Number 2, Part 3  

SciTech Connect (OSTI)

This compilation summarizes significant enforcement actions that have been resolved during the period (July--December 1997) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to material licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication.

NONE

1998-04-01T23:59:59.000Z

329

High temperature materials technology research for advanced thermionic systems. Quarterly progress report, period ending March 31, 1993  

SciTech Connect (OSTI)

Effort was concentrated on modeling the deformation process in refractory alloy single crystals and the stress distribution in metal- ceramic-metal long trilayer insulators. Resolved shear stress distributions are given for a bcc Mo single crystal tube with a [110] growth direction. Effect of 1.8% Nb additions on creep of Mo single crystals was studied, simulating the cylindrical configuration of the TFE emitter. In the area of advanced sheath trilayer insulators, radiation-induced stresses in long cylinder and effect of collector material (Nb vs Mo) were studied. 10 figs, 6 refs.

Zee, R.H.; Rose, M.F.

1993-08-01T23:59:59.000Z

330

Research & Development of Materials/Processing Methods for Continuous Fiber Ceramic Composites (CFCC) Phase 2 Final Report.  

SciTech Connect (OSTI)

The Department of Energy's Continuous Fiber Ceramic Composites (CFCC) Initiative that begun in 1992 has led the way for Industry, Academia, and Government to carry out a 10 year R&D plan to develop CFCCs for these industrial applications. In Phase II of this program, Dow Corning has led a team of OEM's, composite fabricators, and Government Laboratories to develop polymer derived CFCC materials and processes for selected industrial applications. During this phase, Dow Corning carried extensive process development and representative component demonstration activities on gas turbine components, chemical pump components and heat treatment furnace components.

Szweda, A.

2001-01-01T23:59:59.000Z

331

CRADA (AL-C-2009-02) Final Report: Phase I. Lanthanum-based Start Materials for Hydride Batteries  

SciTech Connect (OSTI)

The purpose of Phase I of this work is to focus on developing a La-based start material for making nickel-metal (lanthanum)-hydride batteries based on our carbothermic-silicon process. The goal is to develop a protocol for the manufacture of (La{sub 1-x}R{sub x})(Ni{sub 1-y}M{sub y})(Si{sub z}), where R is a rare earth metal and M is a non-rare earth metal, to be utilized as the negative electrode in nickel-metal hydride (NiMH) rechargeable batteries.

Gschneidner, Jr., Karl [Ames Laboratory; Schmidt, Frederick [Ames Laboratory] [Ames Laboratory; Frerichs, A.E. [Ames Laboratory] [Ames Laboratory; Ament, Katherine A. [Ames Laboratory] [Ames Laboratory

2013-05-01T23:59:59.000Z

332

Testing of candidate materials for their resistance to alkali-vapor adsorption in PFBC and gasification environments. Final report  

SciTech Connect (OSTI)

Laboratory-scale studies were performed to identify metallic material(s) having no, or limited, affinity for alkali vapors in an environment of either the off-gas from pressurized fluidized-bed combustion (PFBC) or the fuel gas from coal gasification. Such materials would be potential candidates for use as components in advanced coal-utilization systems. The following materials were tested for adsorption of NaCl vapor at 870--875 C and atmospheric pressure in a simulated PFBC off-gas (oxidizing) doped with 80 ppmW NaCl vapor: iron-based Type 304 stainless steel (304 SS), nickel-based Hastelloy C-276 and Hastelloy X alloys, cobalt-based Haynes No. 188 alloy, noble-metal-coated 304 SS, aluminized 304 SS, and ZrO{sub 2}-coated 304 SS. The Haynes No. 188 alloy and the aluminized 304 SS were also tested for their NaCl-vapor adsorption in a simulated gasification fuel gas (reducing) under the same test conditions as in the PFBC off-gas test. After 100 h of testing, the specimens were analyzed with a SEM equipped with an energy dispersive X-ray analyzer, and by an AES. The aluminized 304 SS had the least tendency to adsorb NaCl vapor, as well as an excellent resistance to corrosion as a result of the formation of a protective layer of Al{sub 2}O{sub 3} on its surface. In the reducing environment, however, the aluminized 304 SS was badly corroded by H{sub 2}S attack. The Haynes No. 188 showed virtually no NaCl-vapor adsorption and only limited H{sub 2}S attack. The authors recommend further long-term parametric studies to quantitate alkali-vapor adsorption as a function of operating variables for (1) the aluminized 304 SS in the PFBC off-gas environment and (2) the Haynes No. 188 in the gasification fuel gas environment.

Lee, S.H.D.; Natesan, K.; Swift, W.M.

1995-08-01T23:59:59.000Z

333

Use of precalciners to remove alkali from raw materials in the cement industry. Final report, July 1978-July 1980  

SciTech Connect (OSTI)

The objective of this work was to develop an efficient means of removing alkali metal compounds (alkalies) from high-alkali aluminosilicate raw materials of the type commonly used as part of cement raw mixes in order to increase the energy efficiency of cement manufacture. The intention of this project was to determine whether the high-alkali raw materials could be pyroprocessed separately to remove the alkalies before they entered the rotary kiln, where they would be mixed with the other raw feed components. If this could be achieved, considerable savings could be made in the energy required to remove alkalies, compared to conventional methods in which the cement raw mix must be treated as a whole. Two different methods of alkali removal were examined, namely, vaporization of alkalies at relatively low temperatures; and alkali-rich melt separation at relativey high temperatures. The results showed that the removal of alkalies by pyroprocessing of high-alkali raw feed components separate from the other cement raw mix components is not likely to be a practical alternative to the best available conventional precalciner technology. (LCL)

Gartner, E.M.

1980-07-01T23:59:59.000Z

334

Development of a Supercritical Carbon Dioxide Brayton Cycle: Improving VHTR Efficiency and Testing Material Compatibility - Final Report  

SciTech Connect (OSTI)

Generation IV reactors will need to be intrinsically safe, having a proliferation-resistant fuel cycle and several advantages relative to existing light water reactor (LWR). They, however, must still overcome certain technical issues and the cost barrier before it can be built in the U.S. The establishment of a nuclear power cost goal of 3.3 cents/kWh is desirable in order to compete with fossil combined-cycle, gas turbine power generation. This goal requires approximately a 30 percent reduction in power cost for stateof-the-art nuclear plants. It has been demonstrated that this large cost differential can be overcome only by technology improvements that lead to a combination of better efficiency and more compatible reactor materials. The objectives of this research are (1) to develop a supercritical carbon dioxide Brayton cycle in the secondary power conversion side that can be applied to the Very-High-Temperature Gas-Cooled Reactor (VHTR), (2) to improve the plant net efficiency by using the carbon dioxide Brayton cycle, and (3) to test material compatibility at high temperatures and pressures. The reduced volumetric flow rate of carbon dioxide due to higher density compared to helium will reduce compression work, which eventually increase plant net efficiency.

Chang H. Oh

2006-06-01T23:59:59.000Z

335

Hazardous materials in aquatic environments of the Mississippi River Basin. Annual technical report, 30 December 1992--29 December 1993  

SciTech Connect (OSTI)

Tulane and Xavier Universities have singled out the environment as a major strategic focus for research and training for now and beyond the year 2000. In 1989, the Tulane/Xavier Center for Bioenvironmental Research (CBR) was established as the umbrella organization which coordinates environmental research at both universities. In December, 1992, the Tulane/Xavier DBR was awarded a five year grant to study pollution in the Mississippi River system. The ``Hazardous Materials in Aquatic Environments of the Mississippi River Basin`` project is a broad research and education program aimed at elucidating the nature and magnitude of toxic materials that contaminate aquatic environments of the Mississippi River Basin. Studies include defining the complex interactions that occur during the transport of contaminants, the actual and potential impact on ecological systems and health, and the mechanisms through which these impacts might be remediated. The Mississippi River Basin represents a model system for analyzing and solving contamination problems that are found in aquatic systems world-wide. Individual papers have been processed separately for inclusion in the appropriate data bases.

Not Available

1993-12-31T23:59:59.000Z

336

Materials Characterization Center workshop on leaching mechanisms of nuclear waste forms, May 19-21, 1982, Gaithersburg, Maryland. Summary report  

SciTech Connect (OSTI)

This is a report of the second workshop on the leaching mechanism of nuclear waste forms, which was held at Geithersburg, Maryland, May 19-21, 1982. The first session of the workshop was devoted to progress reports by participants in the leaching mechanisms program. These progress reports, as prepared by the participants, are given in Section 3.0. The goal of the remainder of the workshop was to exchange information on the development of repository-relevant leach testing techniques, often called interactions testing. To this end, a wide spectrum of investigators, many of whose work is sponsored by DOE's Nuclear Waste Terminal Storage (NWTS) project, made presentations at the workshop. These presentations were a significant and beneficial part of the workshop and are summarized in Sections 4.0, 5.0 and 6.0 according to the workshop agenda topics. In many cases, the presenters provided a written version of their presentation which has been included verbatim; in the other cases, the workshop chairman has supplied a brief synopsis. Twenty-one papers have been abstracted and indexed for inclusion in the data base.

Mendel, J.E. (comp.)

1982-08-01T23:59:59.000Z

337

Hazardous Material Security (Maryland)  

Broader source: Energy.gov [DOE]

All facilities processing, storing, managing, or transporting hazardous materials must be evaluated every five years for security issues. A report must be submitted to the Department of the...

338

Thermal energy storage in phase change material. Final scientific report 1 Feb 81-31 Jan 82  

SciTech Connect (OSTI)

The present study deals with an experimental investigation of low temperature thermal storage based on macroencapsulation of Phase Change Material (PCM). The storage performance capabilities of capsule bed, tube bank and tubular single-pass heat exchanger are compared. The tests are conducted on the VKI Solar Utility Network (SUN) which is a closed loop facility designed to study air heating systems. An original data acquisition chain based on two conversing microprocessors is developed to carry out mass flow, pressure drop and temperature measurements. The experimental results are interpreted on the basis of comparison with numerical predictions and they allow to draw the following conclusions. Each type of matrix has its own range of operation for practical application but from a heat transfer standpoint, the PCM capsule packing unit is strongly recommended. It is suggested to extend this investigation to the effect of Reynolds number to find optimum range for thermo-mechanical efficiency.

White, P.; Buchlin, J-M.

1982-03-01T23:59:59.000Z

339

Design and fabrication of advanced materials from Illinois coal wastes. Quarterly report, 1 December 1994--28 February 1995  

SciTech Connect (OSTI)

The main goal of this project is to develop a bench-scale procedure to design and fabricate advanced brake and structural composite materials from Illinois coal combustion residues. During the first two quarters of the project, the thrust of the work directed towards characterizing the various coal combustion residues and FGD residue, i.e., scrubber sludge. Scanning electron microscopy (SEM), differential scanning calorimetry (DSC), differential thermal analysis (DTA), and transmission-Fourier transform infrared (FTIR) were conducted on PCC fly ash (Baldwin), FBC fly ash (ADK unit l-6), FBC fly ash (S.I. coal), FBC spent bed ash (ADM, unit l-6), bottom ash, and scrubber sludge (CWLP) residues to characterize their geometrical shapes, mineral phases, and thermal stability. Our spectroscopic results indicate that the scrubber sludge is mainly composed of a gypsum-like phase whose lattice structure is different from the lattice structure of conventional gypsum, and sludge does not contain hannebachite (CaSO{sub 3}.0.5H{sub 2}O) phase. Our attempts to fabricate brake frictional shoes, in the form of 1.25 inch disks, from PCC fly ash, FBC spent bed ash, scrubber sludge, coal char, iron particles, and coal tar were successful. Based on the experience gained and microscopic analyses, we have now upscaled our procedures to fabricate 2.5 inch diameter disk,- from coal combustion residues. This has been achieved. The SEM and Young`s modulus analyses of brake composites fabricated at 400 psi < Pressure < 2200 psi suggest pressure has a strong influence on the particle packing and the filling of interstices in our composites. Also, these results along with mechanical behavior of the fabricated disks lead us to believe that the combination of surface altered PCC fly ash and scrubber sludge particles, together ed ash particles are ideal for our composite materials.

Malhotra, V.M.; Wright, M.A. [Southern Illinois Univ., Carbondale, IL (United States)

1995-12-31T23:59:59.000Z

340

Chemical, biomedical and ecological studies of SRC-I materials from the Fort Lewis Pilot Plant: a status report  

SciTech Connect (OSTI)

This document discusses studies performed with solvent refined coal (SRC) materials obtained from the Fort Lewis Pilot Plant during operation in the SRC-I mode. The development of analytical methodology is presented as well as results obtained from the application of these methods to light oil (LO), wash solvent (WS) and process solvent (PS). Results of cellular and animal studies with LO, WS and PS are included, along with a description of methods for the generation and characterization of LO and PS aerosols, and for exposing rats, mice and guinea pigs to these aerosols. The effects of SRC-I product on seed germination and plant growth which have also been studied are discussed. The SRC-I product, feed coal and the mineral residue have been analyzed for organic and inorganic constituents. The higher-boiling-point material, PS, exhibited significant mutagenic activity in the Ames assay; LO and WS were inactive. Process solvent also caused transformation of cultured Syrian hamster embryo cells. Additional chemical fractionation studies suggest that primary aromatic amines are major determinants of the observed mutagenic activity. Skin-painting studies with SRC-II naphtha, heavy distillate, shale oil and petroleum crude indicate a good correlation between the results of the cellular assays and skin carcinogenesis in mice. Wash solvent was more toxic after oral administration to rats than was light oil or process solvent. The effects of LO, WS and PS on development were studied after administration to pregnant rats. The tissue distribution of a number of components of PS was studied after oral administration of PS to rats. The effect of SRC-I product on the germination and growth of barley was investigated by mixing or layering the product with soil and placing the mixture in a field lysimeter.

Mahlum, D.D. (ed.)

1981-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "materials clsm reported" 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

Regulatory analysis on emergency preparedness for fuel cycle and other radioactive material licensees. Draft report for comment  

SciTech Connect (OSTI)

Potential accidents for 15 types of fuel cycle and other radioactive material licensees were analyzed. The most potentially hazardous accident, by a large margin, was determined to be the sudden rupture of a heated multi-ton cylinder of UF/sub 6/. Acute fatalities offsite are probably not credible. Acute permanent injuries may be possible for many hundreds of meters, and clinically observable transient effects of unknown long term consequences may be possible for distances up to a few miles. These effects would be caused by the chemical toxicity of the UF/sub 6/. Radiation doses would not be significant. The most potentially hazardous accident due to radiation exposure was determined to be a large fire at certain facilities handling large quantities of alpha-emitting radionuclides (i.e., Po-210, Pu-238, Pu-239, Am-241, Cm-242, Cm-244) or radioiodines (I-125 and I-131). However, acute fatalities or injuries to people offsite due to accidental releases of these materials do not seem plausible. The only other significant accident was identified as a long-term pulsating criticality at fuel cycle facilities handling high-enriched uranium or plutonium. An important feature of the most serious accidents is that releases are likely to start without prior warning. The releases would usually end within about half an hour. Thus protective actions would have to be taken quickly to be effective. There is not likely to be enough time for dose projections, complicated decisionmaking during the accident, or the participation of personnel not in the immediate vicinity of the site. The appropriate response by the facility is to immediately notify local fire, police, and other emergency personnel and give them a brief predetermined message recommending protective actions. Emergency personnel are generally well qualified to respond effectively to small accidents of these types.

McGuire, S.A.

1985-06-01T23:59:59.000Z

342

Directory of Certificates of Compliance for radioactive materials packages: Report of NRC approved packages. Volume 1, Revision 18  

SciTech Connect (OSTI)

The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volumes 1 and 2. An alphabetical listing by user name is included in the back of Volume 3 of approved QA programs. The reports include a listing of all users of each package design and approved QA programs prior to the publication date.

NONE

1995-10-01T23:59:59.000Z

343

Diffusion and Leaching Behavior of Radionuclides in Category 3 Waste Encasement Concrete and Soil Fill Material Summary Report  

SciTech Connect (OSTI)

One of the methods being considered for safely disposing of Category 3 low-level radioactive wastes is to encase the waste in concrete. Such concrete encasement would contain and isolate the waste packages from the hydrologic environment and would act as an intrusion barrier. The current plan for waste isolation consists of stacking low-level waste packages on a trench floor, surrounding the stacks with reinforced steel, and encasing these packages in concrete. These concrete-encased waste stacks are expected to vary in size with maximum dimensions of 6.4 m long, 2.7 m wide, and 4 m high. The waste stacks are expected to have a surrounding minimum thickness of 15 cm of concrete encasement. These concrete-encased waste packages are expected to withstand environmental exposure (solar radiation, temperature variations, and precipitation) until an interim soil cover or permanent closure cover is installed, and to remain largely intact thereafter. Any failure of concrete encasement may result in water intrusion and consequent mobilization of radionuclides from the waste packages. The mobilized radionuclides may escape from the encased concrete by mass flow and/or diffusion and move into the surrounding subsurface environment. Therefore, it is necessary to assess the performance of the concrete encasement structure and the ability of the surrounding soil to retard radionuclide migration. The retardation factors for radionuclides contained in the waste packages can be determined from measurements of diffusion coefficients for these contaminants through concrete and fill material. Some of the mobilization scenarios include (1) potential leaching of waste form before permanent closure cover is installed; (2) after the cover installation, long-term diffusion of radionuclides from concrete waste form into surrounding fill material; (3) diffusion of radionuclides from contaminated soils into adjoining concrete encasement and clean fill material. Additionally, the rate of diffusion of radionuclides may be affected by the formation of structural cracks in concrete, the carbonation of the buried waste form, and any potential effect of metallic iron (in the form of rebars) on the mobility of radionuclides. The radionuclides iodine-129 ({sup 129}I), technetium-99 ({sup 99}Tc), and uranium-238 ({sup 238}U) are identified as long-term dose contributors in Category 3 waste (Mann et al. 2001; Wood et al. 1995). Because of their anionic nature in aqueous solutions, {sup 129}I, {sup 99}Tc, and carbonate-complexed {sup 238}U may readily leach into the subsurface environment (Serne et al. 1989, 1992a, b, 1993, and 1995). The leachability and/or diffusion of radionuclide species must be measured to assess the long-term performance of waste grouts when contacted with vadose-zone pore water or groundwater. Although significant research has been conducted on the design and performance of cementitious waste forms, the current protocol conducted to assess radionuclide stability within these waste forms has been limited to the Toxicity Characteristic Leaching Procedure, Method 1311 Federal Registry (EPA 1992) and ANSI/ANS-16.1 leach test (ANSI 1986). These tests evaluate the performance under water-saturated conditions and do not evaluate the performance of cementitious waste forms within the context of waste repositories which are located within water-deficient vadose zones. Moreover, these tests assess only the diffusion of radionuclides from concrete waste forms and neglect evaluating the mechanisms of retention, stability of the waste form, and formation of secondary phases during weathering, which may serve as long-term secondary hosts for immobilization of radionuclides. The results of recent investigations conducted under arid and semi-arid conditions (Al-Khayat et al. 2002; Garrabrants et al. 2002; Garrabrants and Kosson 2003; Garrabrants et al. 2004; Gervais et al. 2004; Sanchez et al. 2002; Sanchez et al. 2003) provide valuable information suggesting structural and chemical changes to concrete waste forms which may affect contaminant containm

Mattigod, Shas V.; Wellman, Dawn M.; Bovaird, Chase C.; Parker, Kent E.; Clayton, Libby N.; Powers, Laura; Recknagle, Kurtis P.; Wood, Marcus I.

2011-08-31T23:59:59.000Z

344

By By-Products Utilization  

E-Print Network [OSTI]

229 1994)." CLSM is primarily used for nonstructural applications such as a backfill material foundations, or as a fill for abandoned tunnels, sewers, storage tanks, etc. Water permeation through CLSM can

Wisconsin-Milwaukee, University of

345

Vehicle Technologies Office: 2010 Lightweight Materials R&D Annual...  

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

0 Lightweight Materials R&D Annual Progress Report Vehicle Technologies Office: 2010 Lightweight Materials R&D Annual Progress Report The Lightweight Materials activity (LM)...

346

Safety Analysis Report for the use of hazardous production materials in photovoltaic applications at the National Renewable Energy Laboratory  

SciTech Connect (OSTI)

To ensure the continued safety of SERI's employees, the community, and the environment, NREL commissioned an internal audit of its photovoltaic operations that used hazardous production materials (HPMs). As a result of this audit, NREL management voluntarily suspended all operations using toxic and/or pyrophoric gases. This suspension affected seven laboratories and ten individual deposition systems. These activities are located in Building 16, which has a permitted occupancy of Group B, Division 2 (B-2). NREL management decided to do the following. (1) Exclude from this SAR all operations which conformed, or could easily be made to conform, to B-2 Occupancy requirements. (2) Include in this SAR all operations that could be made to conform to B-2 Occupancy requirements with special administrative and engineering controls. (3) Move all operations that could not practically be made to conform to B-2 Occupancy requirements to alternate locations. In addition to the layered set of administrative and engineering controls set forth in this SAR, a semiquantitative risk analysis was performed on 30 various accident scenarios. Twelve presented only routine risks, while 18 presented low risks. Considering the demonstrated safe operating history of NREL in general and these systems specifically, the nature of the risks identified, and the layered set of administrative and engineering controls, it is clear that this facility falls within the DOE Low Hazard Class. Each operation can restart only after it has passed an Operational Readiness Review, comparing it to the requirements of this SAR, while subsequent safety inspections will ensure future compliance.

Crandall, R.S.; Nelson, B.P. (National Renewable Energy Lab., Golden, CO (United States)); Moskowitz, P.D.; Fthenakis, V.M. (Brookhaven National Lab., Upton, NY (United States))

1992-07-01T23:59:59.000Z

347

By-Products Utilization  

E-Print Network [OSTI]

-leveling, self-compacting, cementitious material, which has a consistency similar to a pancake batter. CLSM can fibrous residuals from pulp and paper mills. The flowable slurry will meet ACI (American Concrete Institute) 229 recommendations for flowable Controlled Low-Strength Materials (CLSM). CLSM is a self

Wisconsin-Milwaukee, University of

348

Final Report of a CRADA Between Pacific Northwest National Laboratory and the Ford Motor Company (CRADA No. PNNL/265): Deactivation Mechanisms of Base Metal/Zeolite Urea Selective Catalytic Reduction Materials, and Development of Zeolite-Based Hydrocarbon Adsorber Materials  

SciTech Connect (OSTI)

Reducing NOx emissions and particulate matter (PM) are primary concerns for diesel vehicles required to meet current LEV II and future LEV III emission standards which require 90+% NOx conversion. Currently, urea SCR as the NOx reductant and a Catalyzed Diesel Particulate Filter (CDPF) are being used for emission control system components by Ford Motor Company for 2010 and beyond diesel vehicles. Because the use of this technology for vehicle applications is new, the relative lack of experience makes it especially challenging to satisfy durability requirements. Of particular concern is being able to realistically simulate actual field aging of the catalyst systems under laboratory conditions. This is necessary both as a rapid assessment tool for verifying improved performance and certifiability of new catalyst formulations, and to develop a good understanding of deactivation mechanisms that can be used to develop improved catalyst materials. In addition to NOx and PM, the hydrocarbon (HC) emission standards are expected to become much more stringent during the next few years. Meanwhile, the engine-out HC emissions are expected to increase and/or be more difficult to remove. Since HC can be removed only when the catalyst becomes warm enough for its oxidation, three-way catalyst (TWC) and diesel oxidation catalyst (DOC) formulations often contain proprietary zeolite materials to hold the HC produced during the cold start period until the catalyst reaches its operating temperature (e.g., >200C). Unfortunately, much of trapped HC tends to be released before the catalyst reaches the operating temperature. Among materials effective for trapping HC during the catalyst warm-up period, siliceous zeolites are commonly used because of their high surface area and high stability under typical operating conditions. However, there has been little research on the physical properties of these materials related to the adsorption and release of various hydrocarbon species found in the engine exhaust. For these reasons, automakers and engine manufacturers have difficulty improving their catalytic converters for meeting the stringent HC emission standards. In this collaborative program, scientists and engineers in the Institute for Integrated Catalysis at Pacific Northwest National Laboratory and at Ford Motor Company have investigated laboratory- and engine-aged SCR catalysts, containing mainly base metal zeolites. These studies are leading to a better understanding of various aging factors that impact the long-term performance of SCR catalysts and improve the correlation between laboratory and engine aging, saving experimental time and cost. We have also studied materials effective for the temporary storage of HC species during the cold-start period. In particular, we have examined the adsorption and desorption of various HC species produced during the combustion with different fuels (e.g., gasoline, E85, diesel) over potential HC adsorber materials, and measured the kinetic parameters to update Fords HC adsorption model. Since this CRADA has now been completed, in this final report we will provide brief summaries of most of the work carried out on this CRADA over the last several years.

Gao, Feng; Kwak, Ja Hun; Lee, Jong H.; Tran, Diana N.; Peden, Charles HF; Howden, Ken; Cheng, Yisun; Lupescu, Jason; Cavattaio, Giovanni; Lambert, Christine; McCabe, Robert W.

2013-02-14T23:59:59.000Z

349

Design and fabrication of advanced materials from Illinois coal wastes. Quarterly report, 1 March 1995--31 May 1995  

SciTech Connect (OSTI)

The main goal of this project is to develop a bench-scale procedure to design and fabricate advanced brake and structural composite materials from Illinois coal combustion residues. Scanning electron microscopy (SEM), differential scanning calorimetry (DSC), differential thermal analysis (DTA), and transmission-Fourier transform infrared (FTIR) were conducted on PCC fly ash (Baldwin), FBC fly ash (ADM unit1-6), FBC fly ash (S.I. coal), FBC spent bed ash (ADM unit1-6), bottom ash, and scrubber sludge (CWLP) residues to characterize their geometrical shapes, mineral phases, and thermal stability. Our spectroscopic results indicate that the scrubber sludge is mainly composed of a gypsum-like phase whose lattice structure is different from the lattice structure of conventional gypsum, and sludge does not contain hannebachite (CaSO{sub 3}0.5H{sub 2}O) phase. In the second and third quarters the focus of research has been on developing protocols for the formation of advanced brake composites and structural composites. Our attempts to fabricate brake frictional shoes, in the form of 1.25 inch disks, from PCC fly ash, FBC spent bed ash, scrubber sludge, coal char, iron particles, and coal tar were successful. Based on the experience gained and microscopic analyses, we have now upscaled our procedures to fabricate 2.5 inch diameter disks from coal combustion residues. The SEM and Young`s modulus analyses of brake composites fabricated at 400 psi < Pressure < 2200 psi suggest pressure has a strong influence on the particle packing and the filling of interstices in our composites.

Malhotra, V.M.; Wright, M.A.

1995-12-31T23:59:59.000Z

350

Safety Analysis Report for the use of hazardous production materials in photovoltaic applications at the National Renewable Energy Laboratory  

SciTech Connect (OSTI)

To ensure the continued safety of SERI`s employees, the community, and the environment, NREL commissioned an internal audit of its photovoltaic operations that used hazardous production materials (HPMs). As a result of this audit, NREL management voluntarily suspended all operations using toxic and/or pyrophoric gases. This suspension affected seven laboratories and ten individual deposition systems. These activities are located in Building 16, which has a permitted occupancy of Group B, Division 2 (B-2). NREL management decided to do the following. (1) Exclude from this SAR all operations which conformed, or could easily be made to conform, to B-2 Occupancy requirements. (2) Include in this SAR all operations that could be made to conform to B-2 Occupancy requirements with special administrative and engineering controls. (3) Move all operations that could not practically be made to conform to B-2 Occupancy requirements to alternate locations. In addition to the layered set of administrative and engineering controls set forth in this SAR, a semiquantitative risk analysis was performed on 30 various accident scenarios. Twelve presented only routine risks, while 18 presented low risks. Considering the demonstrated safe operating history of NREL in general and these systems specifically, the nature of the risks identified, and the layered set of administrative and engineering controls, it is clear that this facility falls within the DOE Low Hazard Class. Each operation can restart only after it has passed an Operational Readiness Review, comparing it to the requirements of this SAR, while subsequent safety inspections will ensure future compliance.

Crandall, R.S.; Nelson, B.P. [National Renewable Energy Lab., Golden, CO (United States); Moskowitz, P.D.; Fthenakis, V.M. [Brookhaven National Lab., Upton, NY (United States)

1992-07-01T23:59:59.000Z

351

Field application of EMI coatings investigation of coating materials and stylus electroplating protocols for shielded facilities. Final report  

SciTech Connect (OSTI)

To maintain reliable electromagnetic interference (EMI) shielding for electronic equipment shelter interfaces, mating surfaces such as doors and interfaces must provide low contact resistances and be resistant to excessive amounts of corrosion and mechanical wear that would tend to degrade their shielding integrity. The objective of this research was to establish the efficacy of stylus electroplating as a potentially viable field maintenance/repair technique for application of corrosion resistant, wear resistant coatings in order to help maintain the shielding integrity of those interfaces. Aluminum alloy (6061-T6) knife-edge and channel test pieces were stylus electroplated with tin or tin-lead coatings with nickel or copper underlayers. A custom-designed electroplating tool developed for electroplating the complex geometry of a knife-edge substrate appears to provide better control of the plating process and circumvents possible interference with previously deposited areas. This research has resulted in an optimized procedure for producing coatings that exhibit greater adherence, better uniformity, less scarring, and fewer blisters and ridges compared to those previously reported. An optimum electroplating strategy is suggested, which includes applying tin or tin-lead top layers over a thick layer of copper and a thin nickel strike.

Stephenson, L.D.; Donoho, L.H.

1996-03-01T23:59:59.000Z

352

Vehicle Technologies Office: 2010 Propulsion Materials R&D Annual...  

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

0 Propulsion Materials R&D Annual Progress Report Vehicle Technologies Office: 2010 Propulsion Materials R&D Annual Progress Report 2010 annual progress report focusing on enabling...

353

Vehicle Technologies Office: 2012 Propulsion Materials R&D Annual...  

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

2012 Propulsion Materials R&D Annual Progress Report Vehicle Technologies Office: 2012 Propulsion Materials R&D Annual Progress Report 2012 annual progress report focusing on...

354

Vehicle Technologies Office: 2013 Propulsion Materials R&D Annual...  

Energy Savers [EERE]

3 Propulsion Materials R&D Annual Progress Report Vehicle Technologies Office: 2013 Propulsion Materials R&D Annual Progress Report This report describes the progress made during...

355

Reports  

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

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

356

REPORT  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Careerlumens_placard-green.epsEnergy1.pdfMarket37963American |Purpose This procedurenote: The REPORT

357

NERI FINAL TECHNICAL REPORT, DE-FC07-O5ID14647, OPTIMIZATION OF OXIDE COMPOUNDS FOR ADVANCED INERT MATRIX MATERIALS  

SciTech Connect (OSTI)

In order to reduce the current excesses of plutonium (both weapon grade and reactor grade) and other transuranium elements, a concept of inert matrix fuel (IMF) has been proposed for an uranium free transmutation of fissile actinides which excludes continuous uranium-plutonium conversion in thermal reactors and advanced systems. Magnesium oxide (MgO) is a promising candidate for inert matrix (IM) materials due to its high melting point (2827 C), high thermal conductivity (13 W/K {center_dot} m at 1000 C), good neutronic properties, and irradiation stability However, MgO reacts with water and hydrates easily, which prevents it from being used in light water reactors (LWRs) as an IM. To improve the hydration resistance of MgO-based inert matrix materials, Medvedev and coworkers have recently investigated the introduction of a secondary phase that acts as a hydration barrier. An MgO-ZrO{sub 2} composite was specifically studied and the results showed that the composite exhibited improved hydration resistance than pure MgO. However, ZrO{sub 2} is insoluble in most acids except HF, which is undesirable for fuel reprocessing. Moreover, the thermal conductivity of ZrO{sub 2} is low and typically less than 3 W {center_dot} m{sup -1} {center_dot} K{sup -1} at 1000 C. In search for an alternative composite strategy, Nd{sub 2}Zr{sub 2}O{sub 7}, an oxide compound with pyrochlore structure, has been proposed recently as a corrosion resistant phase, and MgO-Nd{sub 2}Zr{sub 2}O{sub 7} composites have been investigated as potential IM materials. An adequate thermal conductivity of 6 W {center_dot} m{sup -} 1 {center_dot} K{sup -1} at 1000 C for the MgO-Nd{sub 2}Zr{sub 2}O{sub 7} composite with 90 vol% MgO was recently calculated and reported. Other simulations proposed that the MgO-pyrochlore composites could exhibit higher radiation stability than previously reported. Final optimization of the composite microstructure was performed on the 70 vol% MgO-Nd{sub 2}Zr{sub 2}O{sub 7} composite that burnup calculations had shown to have the closest profile to that of MOX fuel. Theoretical calculations also indicated that a homogeneous 70 vol% MgO composite could achieve the desired microstructure that would result in satisfying the dual requirements of good thermal properties.

PI: JUAN C. NINO, ASSOCIATE PROFESSOR

2009-01-11T23:59:59.000Z

358

Spent Fuel Working Group report on inventory and storage of the Department`s spent nuclear fuel and other reactor irradiated nuclear materials and their environmental, safety and health vulnerabilities. Volume 3, Site team reports  

SciTech Connect (OSTI)

A self assessment was conducted of those Hanford facilities that are utilized to store Reactor Irradiated Nuclear Material, (RINM). The objective of the assessment is to identify the Hanford inventories of RINM and the ES & H concerns associated with such storage. The assessment was performed as proscribed by the Project Plan issued by the DOE Spent Fuel Working Group. The Project Plan is the plan of execution intended to complete the Secretary`s request for information relevant to the inventories and vulnerabilities of DOE storage of spent nuclear fuel. The Hanford RINM inventory, the facilities involved and the nature of the fuel stored are summarized. This table succinctly reveals the variety of the Hanford facilities involved, the variety of the types of RINM involved, and the wide range of the quantities of material involved in Hanford`s RINM storage circumstances. ES & H concerns are defined as those circumstances that have the potential, now or in the future, to lead to a criticality event, to a worker radiation exposure event, to an environmental release event, or to public announcements of such circumstances and the sensationalized reporting of the inherent risks.

Not Available

1993-11-01T23:59:59.000Z

359

Reflectance Function Approximation for Material Classification  

E-Print Network [OSTI]

Reflectance Function Approximation for Material Classification Edward Wild CS 766 Final Project This report summarizes the results of a project to approximate reflectance functions and classify materials to classify materials. Classification algorithms are proposed to deal with unseen materials. Experimental

Dyer, Charles R.

360

METC/3M Cooperative Agreement CRADA 94-024 high temperature high pressure filter materials exposure test program. Volume 1, Final report  

SciTech Connect (OSTI)

In conjunction with shakedown, operation, and desulfurization testing at the Morgantown Energy Technology Center (METC) 10 in. Fluid Bed Gasification and Cleanup facility, a series of tests was completed in cooperation with the Minnesota Mining and Manufacturing Company (3M). This cooperative research and development agreement (CRADA) between METC and 3M was to evaluate exposure of 3M SICONEX{trademark} fiber-reinforced ceramic and NEXTEL{trademark} 312 and 550 ceramic fabric materials to a gasifying environment at high temperatures (1000--1100{degree}F) and high pressure (300 psia). Minnesota Mining and Manufacturing Company (3M) provided two 60 mm I.D. {times} 0.5 m SICONEX{trademark} spools and one each of the NEXTEL{trademark} 312 and 550 ceramic fabrics for exposure to coal gas from the METC gasifier. METC installed the materials in a vessel existing in the METC Cleanup Facility and provided process data in exchange for ceramic filter and ash/char characterization. Details of the CRADA are found in CRADA 94-024. This report contains METC`s contribution to CRADA 94-024. Four gasifier runs were conducted over a five month period to accumulate 483 hours of operation. During this time, 2 LayCer{trademark} 70/3 filters were used for filtering the coal gas while the SICONEX{trademark} and NEXTEL{trademark} were exposed along side of the filters. During one 89 hour test, one Laycer{trademark} 70/3 candle was installed with a 3M ceramic composite filter. The face velocity through the candles was maintained nominally at 2.5 ft/min throughout the testing.

NONE

1995-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "materials clsm reported" 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

When and how to end shelter-in-place protection from a release of airborne hazardous material : report on a decision-making concept and methodology.  

SciTech Connect (OSTI)

Shelter-in-place (SIP) is considered a credible alternative to immediate evacuation to protect the population on and around Army chemical warfare agent stockpile storage sites from accidental agent releases of short duration. To be effective, this strategy requires immediate SIP to minimize initial exposure to agent vapor, followed by timely and appropriate termination of SIP to minimize additional exposure to agent vapor accumulations in the shelter when the air outside becomes less hazardous. However, a major challenge facing emergency managers has been how to decide the best time and way to end SIP to obtain this ideal. This report describes a concept to make this decision, and suggests a methodology to apply the concept as a site-specific response tool. The major conditions that influence the exposure of a population are the source term values of the agent that is released, meteorological conditions, shelter air change rates, the distance of the shelter from the source, and th e dose-response relationship of the hazardous material. The circumstances that contribute to overall exposure associated with a SIP strategy involve exposure during the time before taking shelter, exposure while sheltered due to vapor infiltration, and additional exposure (if any) following the termination of SIP. Options to end SIP are to resume normal activities with no restrictions, to ventilate the shelter but remain indoors, to exit from the shelter and remain nearby, or to relocate to a designated facility. The optimal time and way to end SIP involves examining the relationships among the conditions and circumstances listed above to find the combination of these variables that gives the smallest area where a sheltered population might receive a certain level of toxic effect. For example, find the combination of times, conditions, and circumstances that produce the smallest area where fatalities are possible. In this case, the best time and action to end SIP to minimize fatalities is that combination of variables which produces the smallest area where this level of effect is expected. The methodology to apply the concept is to use a computer model to examine the relationships among these conditions and circumstances (many of which are pre-planned default inputs), and display the best time and action to end SIP quickly, in a user-friendly format. A computer model that was developed to prove the concept and demonstrate the methodology (called the TSIP Model) is described in the report, and the use of the TSIP Model is illustrated in a case study in an appendix to the report. The report also discusses public education and emergency instructions essential for implementing this concept, and makes recommendations for agreements, plans, and exercises relevant to deciding when and how to end SIP. This concept and methodology is independent of the atmospheric dispersion model used, and is not limited to chemical warfare agent vapor hazards. Thus it can help make decisions on when and how to end SIP following the accidental release of many other non-flammable non-reactive hazardous vapors if sufficient information is available about the characteristics of the material and the circumstances of the release.

Yantosik, G.; Lerner, K.; Maloney, D.; Wasmer, F.

2002-02-13T23:59:59.000Z

362

Addendum to the Corrective Action Decision Document/Closure Report for Corrective Action Unit 529: Area 25 Contaminated Materials, Nevada Test Site, Nevada, Revision 1  

SciTech Connect (OSTI)

This document constitutes an addendum to the Corrective Action Decision Document/Closure Report for Corrective Action Unit 529: Area 25 Contaminated Materials, Nevada Test Site, Nevada as described in the document Recommendations and Justifications To Remove Use Restrictions Established under the U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office Federal Facility Agreement and Consent Order dated September 2013. The Use Restriction (UR) Removal document was approved by the Nevada Division of Environmental Protection on October 16, 2013. The approval of the UR Removal document constituted approval of each of the recommended UR removals. In conformance with the UR Removal document, this addendum consists of: This page that refers the reader to the UR Removal document for additional information The cover, title, and signature pages of the UR Removal document The NDEP approval letter The corresponding section of the UR Removal document This addendum provides the documentation justifying the cancellation of the UR for CAS 25-23-17, Contaminated Wash (Parcel H). This UR was established as part of FFACO corrective actions and was based on the presence of total petroleum hydrocarbon diesel-range organics contamination at concentrations greater than the NDEP action level at the time of the initial investigation.

Krauss, Mark J

2013-10-01T23:59:59.000Z

363

Tulane/Xavier University Hazardous Materials in Aquatic Environments of the Mississippi River Basin. Quarterly progress report, January 1, 1995--March 31, 1995  

SciTech Connect (OSTI)

This progress report covers activities for the period January 1 - March 31, 1995 on project concerning `Hazardous Materials in Aquatic Environments of the Mississippi River Basin.` The following activities are each summarized by bullets denoting significant experiments/findings: biotic and abiotic studies on the biological fate, transport and ecotoxicity of toxic and hazardous waste in the Mississippi River Basin; assessment of mechanisms of metal-induced reproductive toxicity in quatic species as a biomarker of exposure; hazardous wastes in aquatic environments: biological uptake and metabolism studies; ecological sentinels of aquatic contamination in the lower Mississippi River system; bioremediation of selected contaminants in aquatic environments of the Mississippi River Basin; a sensitive rapid on-sit immunoassay for heavy metal contamination; pore-level flow, transport, agglomeration and reaction kinetics of microorganism; biomarkers of exposure and ecotoxicity in the Mississippi River Basin; natural and active chemical remediation of toxic metals, organics and radionuclides in the aquatic environment; expert geographical information systems for assessing hazardous wastes in aquatic environments; enhancement of environmental education; and a number of just initiated projects including fate and transport of contaminants in aquatic environments; photocatalytic remediation; radionuclide fate and modeling from Chernobyl.

NONE

1995-05-01T23:59:59.000Z

364

Materials Characterization Center state-of-the-art report on corrosion data pertaining to metallic barriers for nuclear-waste repositories  

SciTech Connect (OSTI)

A compilation of published corrosion data on metals that have been suggested as canisters and overpack materials is presented. The data were categorized according to the solutions used in testing and divided into two parts: high-ionic strength solutions (such as seawater and brine) and low-ionic-strength waters (such as basalt and tuff waters). This distinction was made primarily because of the general difference in aggressiveness of these solutions with respect to general corrosion. A considerable amount of data indicated that titanium alloys have acceptably low uniform corrosion rates in anticipated repository sites; the other possible corrosion failure modes for titanium alloys, such as stress corrosion cracking and delayed failure due to hydrogen, have not been sufficiently studied to make any similar conclusions about lifetime with respect to these particular degradation processes. Other data suggested that iron-base alloys are sufficiently resistant to corrosion in basalt and tuff waters, although the effects of radiation and radiation combined with elevated temperature have not been reported in enough detail to conclusively qualify iron-base alloys for any particular barrier thickness in regard to uniform corrosion rate. The effect of overpack size on corrosion rate has been given little attention. A review of long-term underground data indicated that temperature and accessibility to oxygen were too different for deep geologic repositories to make the underground corrosion data directly applicable. However, the characteristics of corrosion attack, statistical treatment of data, and kinetics of corrosion showed that corrosion proceeds in a systematic and predictable way.

Merz, M.D.

1982-10-01T23:59:59.000Z

365

2010 Manufacturing Readiness Assessment Update to the 2008 Report for Fuel Cell Stacks and Systems for the Backup Power and Materials Handling Equipment Markets  

SciTech Connect (OSTI)

In 2008, the National Renewable Energy Laboratory (NREL), under contract to the US Department of Energy (DOE), conducted a manufacturing readiness assessment (MRA) of fuel cell systems and fuel cell stacks for back-up power and material handling applications (MHE). To facilitate the MRA, manufacturing readiness levels (MRL) were defined that were based on the Technology Readiness Levels previously established by the US Department of Energy (DOE). NREL assessed the extensive existing hierarchy of MRLs developed by Department of Defense (DoD) and other Federal entities, and developed a MRL scale adapted to the needs of the Fuel Cell Technologies Program (FCTP) and to the status of the fuel cell industry. The MRL ranking of a fuel cell manufacturing facility increases as the manufacturing capability transitions from laboratory prototype development through Low Rate Initial Production to Full Rate Production. DOE can use MRLs to address the economic and institutional risks associated with a ramp-up in polymer electrolyte membrane (PEM) fuel cell production. In 2010, NREL updated this assessment, including additional manufacturers, an assessment of market developments since the original report, and a comparison of MRLs between 2008 and 2010.

Wheeler, D.; Ulsh, M.

2012-08-01T23:59:59.000Z

366

Thin Film Materials and Processing Techniques for a Next Generation Photovoltaic Device: Cooperative Research and Development Final Report, CRADA Number CRD-12-470  

SciTech Connect (OSTI)

This research extends thin film materials and processes relevant to the development and production of a next generation photovoltaic device.

van Hest, M.

2013-08-01T23:59:59.000Z

367

Determination of the relative resistance to ignition of selected turbopump materials in high-pressure, high-temperature, oxygen environments, volume 3. Interim report  

SciTech Connect (OSTI)

Data is presented from frictional heating tests on pairs of different materials. Materials tested include: Hastelloy X, Inconel 600, Invar 36, Monel K-500, Monel 400, nickel 200, silicon carbide, stainless steels 316, and zirconium copper. In tests where pairs of different materials were rubbed together, the material rated less resistant to ignition in previous tests appeared to control the resistance to ignition of the pair.

Stoltzfus, J.M.; Benz, F.J.

1986-07-01T23:59:59.000Z

368

University of Illinois at Urbana-Champaign, Materials Research Laboratory progress report for FY 1993 and research proposal for FY 1994  

SciTech Connect (OSTI)

The materials research laboratory program is about 30% of total Materials Science and Engineering effort on the Univ. of Illinois campus. Coordinated efforts are being carried out in areas of structural ceramics, grain boundaries, field responsive polymeric and organic materials, molecular structure of solid-liquid interfaces and its relation to corrosion, and x-ray scattering science.

Birnbaum, H.K.

1993-03-01T23:59:59.000Z

369

Chemical and Oil Spill/Release Clean-Up and Reporting Requirements Chemicals and oils are used throughout Penn State University. Chemicals may be loosely defined as any material  

E-Print Network [OSTI]

Chemical and Oil Spill/Release Clean-Up and Reporting Requirements Chemicals and oils are used, reactive, flammable, or toxic. This can include, for example, oil-based paints, alcohol, WD-40, and any number of laboratory materials. Oils include petroleum products, vegetable oils, hydraulic and mineral

Maroncelli, Mark

370

Transmission Project Reporting FPA 216h | Department of Energy  

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

Disturbance Events Incident Reporting Emergency Situation Reports Energy Assurance Daily Transmission Project Reporting Library New Reports & Other Materials Meetings & Events...

371

Final Report - Recovery Act - Development and application of processing and process control for nano-composite materials for lithium ion batteries  

SciTech Connect (OSTI)

Oak Ridge National Laboratory and A123 Systems, Inc. collaborated on this project to develop a better understanding, quality control procedures, and safety testing for A123 System s nanocomposite separator (NCS) technology which is a cell based patented technology and separator. NCS demonstrated excellent performance. x3450 prismatic cells were shown to survive >8000 cycles (1C/2C rate) at room temperature with greater than 80% capacity retention with only NCS present as an alternative to conventional polyolefin. However, for a successful commercialization, the coating conditions required to provide consistent and reliable product had not been optimized and QC techniques for being able to remove defective material before incorporation into a cell had not been developed. The work outlined in this report addresses these latter two points. First, experiments were conducted to understand temperature profiles during the different drying stages of the NCS coating when applied to both anode and cathode. One of the more interesting discoveries of this study was the observation of the large temperature decrease experienced by the wet coating between the end of the infrared (IR) drying stage and the beginning of the exposure to the convection drying oven. This is not a desirable situation as the temperature gradient could have a deleterious effect on coating quality. Based on this and other experimental data a radiative transfer model was developed for IR heating that also included a mass transfer module for drying. This will prove invaluable for battery coating optimization especially where IR drying is being employed. A stress model was also developed that predicts that under certain drying conditions tensile stresses are formed in the coating which could lead to cracking that is sometimes observed after drying is complete. Prediction of under what conditions these stresses form is vital to improving coating quality. In addition to understanding the drying process other parameters such as slurry quality and equipment optimization were examined. Removal of particles and gels by filtering, control of viscosity by %solids and mixing adjustments, removal of trapped gas in the slurry and modification of coater speed and slot die gap were all found to be important for producing uniform and flaw-free coatings. Second, an in-line Hi-Pot testing method has been developed specifically for NCS that will enable detection of coating flaws that could lead to soft or hard electrical shorts within the cell. In this way flawed material can be rejected before incorporation into the cell thus greatly reducing the amount of scrap that is generated. Improved battery safety is an extremely important benefit of NCS. Evaluation of battery safety is usually accomplished by conducting a variety of tests including nail penetration, hot box, over charge, etc. For these tests entire batteries must be built but the resultant temperature and voltage responses reveal little about the breakdown mechanism. In this report is described a pinch test which is used to evaluate NCS quality at various stages including coated anode and cathode as well as assembled cell. Coupled with post-microscopic examination of the damaged pinch point test data can assist in the coating optimization from an improved end-use standpoint. As a result of this work two invention disclosures, one for optimizing drying methodology and the other for an in-line system for flaw detection, have been filed. In addition, 2 papers are being written for submission to peer-reviewed journals.

Daniel, Claus [ORNL; Armstrong, Beth L [ORNL; Maxey, L Curt [ORNL; Sabau, Adrian S [ORNL; Wang, Hsin [ORNL; Hagans, Patrick [A123 Systems, Inc.; Babinec, Sue [A123 Systems, Inc.

2013-08-01T23:59:59.000Z

372

CRADA Final Report for NFE-08-01826: Development and application of processing and processcontrol for nano-composite materials for lithium ion batteries  

SciTech Connect (OSTI)

Oak Ridge National Laboratory and A123 Systems, Inc. collaborated on this project to develop a better understanding, quality control procedures, and safety testing for A123 Systems nanocomposite separator (NCS) technology which is a cell based patented technology and separator. NCS demonstrated excellent performance. x3450 prismatic cells were shown to survive >8000 cycles (1C/2C rate) at room temperature with greater than 80% capacity retention with only NCS present as an alternative to conventional polyolefin. However, for a successful commercialization, the coating conditions required to provide consistent and reliable product had not been optimized and QC techniques for being able to remove defective material before incorporation into a cell had not been developed. The work outlined in this report addresses these latter two points. First, experiments were conducted to understand temperature profiles during the different drying stages of the NCS coating when applied to both anode and cathode. One of the more interesting discoveries of this study was the observation of the large temperature decrease experienced by the wet coating between the end of the infrared (IR) drying stage and the beginning of the exposure to the convection drying oven. This is not a desirable situation as the temperature gradient could have a deleterious effect on coating quality. Based on this and other experimental data a radiative transfer model was developed for IR heating that also included a mass transfer module for drying. This will prove invaluable for battery coating optimization especially where IR drying is being employed. A stress model was also developed that predicts that under certain drying conditions tensile stresses are formed in the coating which could lead to cracking that is sometimes observed after drying is complete. Prediction of under what conditions these stresses form is vital to improving coating quality. In addition to understanding the drying process other parameters such as slurry quality and equipment optimization were examined. Removal of particles and gels by filtering, control of viscosity by %solids and mixing adjustments, removal of trapped gas in the slurry and modification of coater speed and slot die gap were all found to be important for producing uniform and flaw-free coatings. Second, an in-line Hi-Pot testing method has been developed specifically for NCS that will enable detection of coating flaws that could lead to soft or hard electrical shorts within the cell. In this way flawed material can be rejected before incorporation into the cell thus greatly reducing the amount of scrap that is generated. Improved battery safety is an extremely important benefit of NCS. Evaluation of battery safety is usually accomplished by conducting a variety of tests including nail penetration, hot box, over charge, etc. For these tests entire batteries must be built but the resultant temperature and voltage responses reveal little about the breakdown mechanism. In this report is described a pinch test which is used to evaluate NCS quality at various stages including coated anode and cathode as well as assembled cell. Coupled with post-microscopic examination of the damaged pinch point test data can assist in the coating optimization from an improved end-use standpoint. As a result of this work two invention disclosures, one for optimizing drying methodology and the other for an in-line system for flaw detection, have been filed. In addition, 2 papers are being written for submission to peer-reviewed journals.

Daniel, C.; Armstrong, B.; Maxey, C.; Sabau, A.; Wang, H.; Hagans, P. (A123 Systems, Inc.); and Babinec, S. (A123 Systems, Inc.)

2012-12-15T23:59:59.000Z

373

Safety analysis report for the use of hazardous production materials in photovoltaic applications at the National Renewable Energy Laboratory. Volume 2, Appendices  

SciTech Connect (OSTI)

To ensure the continued safety of SERI`s employees, the community, and the environment, NREL commissioned an internal audit of its photovoltaic operations that used hazardous production materials (HPMS). As a result of this audit, NREL management voluntarily suspended all operations using toxic and/or pyrophoric gases. This suspension affected seven laboratories and ten individual deposition systems. These activities are located in Building 16, which has a permitted occupancy of Group B, Division 2 (B-2). NREL management decided to do the following. (1) Exclude from this SAR all operations which conformed, or could easily be made to conform, to B-2 Occupancy requirements. (2) Include in this SAR all operations that could be made to conform to B-2 Occupancy requirements with special administrative and engineering controls. (3) Move all operations that could not practically be made to conform to B-2 occupancy requirements to alternate locations. In addition to the layered set of administrative and engineering controls set forth in this SAR, a semiquantitative risk analysis was performed on 30 various accident scenarios. Twelve presented only routine risks, while 18 presented low risks. Considering the demonstrated safe operating history of NREL in general and these systems specifically, the nature of the risks identified, and the layered set of administrative and engineering controls, it is clear that this facility falls within the DOE Low Hazard Class. Each operation can restart only after it has passed an Operational Readiness Review, comparing it to the requirements of this SAR, while subsequent safety inspections will ensure future compliance. This document contains the appendices to the NREL safety analysis report.

Crandall, R.S.; Nelson, B.P.; Moskowitz, P.D.; Fthenakis, V.M.

1992-07-01T23:59:59.000Z

374

EV Everywhere Workshop: Electric Motors and Critical Materials...  

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

Electric Motors and Critical Materials Breakout Group Report EV Everywhere Workshop: Electric Motors and Critical Materials Breakout Group Report Presentation given at the EV...

375

Vehicle Technologies Office: 2008 Propulsion Materials R&D Annual...  

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

8 Propulsion Materials R&D Annual Progress Report Vehicle Technologies Office: 2008 Propulsion Materials R&D Annual Progress Report 2008propulsionmaterials.pdf More Documents &...

376

Vehicle Technologies Office: 2011 Propulsion Materials R&D Annual...  

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

Vehicle Technologies Office: 2011 Propulsion Materials R&D Annual Progress Report Vehicle Technologies Office: 2011 Propulsion Materials R&D Annual Progress Report 2011 annual...

377

Vehicle Technologies Office: 2009 Propulsion Materials R&D Annual...  

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

9 Propulsion Materials R&D Annual Progress Report Vehicle Technologies Office: 2009 Propulsion Materials R&D Annual Progress Report 2009propulsionmaterials.pdf More Documents &...

378

Evaluation of Novel Semiconductor Materials Potentially Useful in Solar Cells: Cooperative Research and Development Final Report, CRADA number CRD-06-00172  

SciTech Connect (OSTI)

Evaluation of novel semiconductor materials potentially useful in solar cells. NREL will fabricate, test and analyze solar cells from EpiWorks' wafers produced in 2-3 separate growth campaigns. NREL will also characterize material from 2-3 separate EpiWorks material development campaigns. Finally, NREL will visit EpiWorks and help establish any necessary process, such as spectral CV measurements and III-V on Si metalization processes and help validate solar cell designs and performance.

Geisz, J.

2010-07-01T23:59:59.000Z

379

Chemistry and Materials Science Weapons-Supporting Research and Laboratory-Directed Research and Development. Second half progress report, FY 1993  

SciTech Connect (OSTI)

Thrust areas of the weapons-supporting research are surface research, uranium research, physics and processing of metals, energetic materials. Group study areas included strength of Al and Al-Mg/alumina bonds, advanced synchrotron radiation study of materials, and theory, modeling, and computation. Individual projects were life prediction for composites and thermoelectric materials with exceptional figures of merit. The laboratory-directed R and D include director`s initiatives (aerogel-based electronic devices, molecular levels of energetic materials), individual projects, and transactinium institute studies. An author index is provided.

Not Available

1994-02-01T23:59:59.000Z

380

Mobility of Tritium in Engineered and Earth Materials at the NuMI Facility, Fermilab: Progress report for work performed between June 13 and September 30, 2006  

E-Print Network [OSTI]

tritium transport in porous materials (concrete, rock) andsaturated concrete during drying, Trans. Porous Media , 24,porous medium given the diffusivity in free water. The concrete

2006-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "materials clsm reported" 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

Fossil Energy Advanced Research and Technology Development (AR&TD) Materials Program semiannual progress report for the period ending September 30, 1991. Fossil Energy Program  

SciTech Connect (OSTI)

The objective of the Fossil Energy Advanced Research and Technology Development Materials Program is to conduct research and development on materials for fossil energy applications with a focus on the longer-term and generic needs of the various fossil fuel technologies. The Program includes research aimed toward a better understanding of materials behavior in fossil energy environments and the development of new materials capable of substantial enhancement of plant operations and reliability. Research is outlined in four areas: Ceramics, New Alloys, Corrosion and Erosion Research, and Technology Development and Transfer. (VC)

Judkins, R.R.; Cole, N.C. [comps.

1992-04-01T23:59:59.000Z

382

Fossil Energy Advanced Research and Technology Development (AR TD) Materials Program semiannual progress report for the period ending September 30, 1991  

SciTech Connect (OSTI)

The objective of the Fossil Energy Advanced Research and Technology Development Materials Program is to conduct research and development on materials for fossil energy applications with a focus on the longer-term and generic needs of the various fossil fuel technologies. The Program includes research aimed toward a better understanding of materials behavior in fossil energy environments and the development of new materials capable of substantial enhancement of plant operations and reliability. Research is outlined in four areas: Ceramics, New Alloys, Corrosion and Erosion Research, and Technology Development and Transfer. (VC)

Judkins, R.R.; Cole, N.C. (comps.)

1992-04-01T23:59:59.000Z

383

Storage and disposition of weapons usable fissile materials (FMD) PEIS: Blending of U-233 to {lt}12% or {lt}5% enrichment at the Idaho National Engineering Laboratory. Data report, Draft: Version 1  

SciTech Connect (OSTI)

Uranium-233 (U-233), a uranium isotope, is a fissionable material capable of fueling nuclear reactors or being utilized in the manufacturing of nuclear weapons. As such, it is controlled as a special nuclear material. The Idaho National Engineering Laboratory (INEL) and Oak Ridge National Laboratory (ORNL) currently store the Department of Energy`s (DOE`s) supply of unirradiated U-233 fuel materials. Irradiated U-233 is covered by the national spent nuclear fuel (SNF) program and is not in the scope of this report. The U-233 stored at ORNL is relatively pure uranium oxide in the form of powder or monolithic solids. This material is currently stored in stainless steel canisters of variable lengths measuring about 3 inches in diameter. The ORNL material enrichment varies with some material containing considerable amounts of U-235. The INEL material is fuel from the Light Water Breeder Reactor (LWBR) Program and consists of enriched uranium and thorium oxides in zircaloy cladding. The DOE inventory of U-233 contains trace quantities of U-232, and daughter products from the decay of U-232 and U-233, resulting in increased radioactivity over time. These increased levels of radioactivity generally result in the need for special handling considerations.

Shaber, E.L.

1995-08-01T23:59:59.000Z

384

Materials Scientist  

Broader source: Energy.gov [DOE]

Alternate Title(s):Materials Research Engineer; Metallurgical/Chemical Engineer; Product Development Manager;

385

Determination of the relative resistance to ignition of selected turbopump materials in high-pressure, high-temperature, oxygen environments, volume 2. Interim report  

SciTech Connect (OSTI)

Data from the particle impact tests are presented. Results are provided for the frictional heating tests of pairs of like materials. The materials tested include: Hastelloy X, Inconel 600, Invar 36, Monel K-500, Monel 400, nickel 200, silicon carbide, stainless steel 316, and zironium copper.

Stoltzfus, J.M.; Benz, F.J.

1986-07-01T23:59:59.000Z

386

Materials Science and Technology Division light-water-reactor safety research program. Quarterly progress report, July-September 1983. Volume 3  

SciTech Connect (OSTI)

This progress report summarizes the Argonne National Laboratory work performed during July, August, and September 1983 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors (reported elsewhere), Transient Fuel Response and Fission Product Release, Clad Properties for Code Verification, and Long-Term Embrittlement of Cast Duplex Stainless Steels in LWR Systems (reported elsewhere).

Not Available

1984-07-01T23:59:59.000Z

387

Corrective Action Decision Document/Closure Report for Corrective Action Unit 545: Dumps, Waste Disposal Sites, and Buried Radioactive Materials Nevada Test Site, Nevada, Revision 0  

SciTech Connect (OSTI)

This Corrective Action Decision Document (CADD)/Closure Report (CR) has been prepared for Corrective Action Unit (CAU) 545, Dumps, Waste Disposal Sites, and Buried Radioactive Materials, in Areas 2, 3, 9, and 20 of the Nevada Test Site, Nevada, in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management (1996, as amended February 2008). Corrective Action Unit 545 is comprised of the following eight Corrective Action Sites (CASs): 02-09-01, Mud Disposal Area 03-08-03, Mud Disposal Site 03-17-01, Waste Consolidation Site 3B 03-23-02, Waste Disposal Site 03-23-05, Europium Disposal Site 03-99-14, Radioactive Material Disposal Area 09-23-02, U-9y Drilling Mud Disposal Crater 20-19-01, Waste Disposal Site While all eight CASs are addressed in this CADD/CR, sufficient information was available for the following three CASs; therefore, a field investigation was not conducted at these sites: For CAS 03-08-03, though the potential for subsidence of the craters was judged to be extremely unlikely, the data quality objective (DQO) meeting participants agreed that sufficient information existed about disposal and releases at the site and that a corrective action of close in place with a use restriction is recommended. Sampling in the craters was not considered necessary. For CAS 03-23-02, there were no potential releases of hazardous or radioactive contaminants identified. Therefore, the Corrective Action Investigation Plan for CAU 545 concluded that: Sufficient information exists to conclude that this CAS does not exist as originally identified. Therefore, there is no environmental concern associated with CAS 03-23-02. This CAS is closed with no further action. For CAS 03-23-05, existing information about the two buried sources and lead pig was considered to be sufficient, and safety concerns existed about the stability of the crater component. Therefore, a corrective action of close in place with a use restriction is recommended, and sampling at the site was not considered necessary. The purpose of this CADD/CR is to provide justification and documentation to support the recommendation for closure of CAU 545 with no further corrective action. To achieve this, corrective action investigation (CAI) activities were performed from August 20 through November 02, 2007, as set forth in the CAU 545 Corrective Action Investigation Plan. The purpose of the CAI was to fulfill the following data needs as defined during the DQO process: Determine whether contaminants of concern (COCs) are present. If COCs are present, determine their nature and extent. Provide sufficient information and data to complete appropriate corrective actions. The CAU 545 dataset from the investigation results was evaluated based on the data quality indicator parameters. This evaluation demonstrated the quality and acceptability of the dataset for use in fulfilling the DQO data needs. Analytes detected during the CAI were evaluated against final action levels established in this CADD/CR. The results of the CAI identified no COCs at the five CASs investigated in CAU 545. As a best management practice, repair of the fence enclosing CAS 03-08-03 has been completed. Therefore, the DOE, National Nuclear Security Administration Nevada Site Office provides the following recommendations: Close in place COCs at CASs 03-08-03 and 03-23-05 with use restrictions. No further corrective action for CAU 545. No Corrective Action Plan. Corrective Action Unit 545 should be moved from Appendix III to Appendix IV of the Federal Facility Agreement and Consent Order. A Notice of Completion to the DOE, National Nuclear Security Administration Nevada Site Office is requested from the Nevada Division of Environmental Protection for closure of CAU 545.

Alfred Wickline

2008-04-01T23:59:59.000Z

388

Final Technical Report on DE-SC00002460 [Bimetallic or trimetallic materials with structural metal centers based on Mn, Fe or V  

SciTech Connect (OSTI)

Bimetallic or trimetallic materials with structural metal centers based on Mn, Fe or V were investigated under this project. These metal centers are the focus of this research as they have high earth abundance and have each shown success as cathode materials in lithium batteries. Silver ion, Ag{sup +}, was initially selected as the displacement material as reduction of this center should result in increased conductivity as Ag{sup 0} metal particles are formed in-situ upon electrochemical reduction. The in-situ formation of metal nanoparticles upon electrochemical reduction has been previously noted, and more recently, we have investigated the resulting increase in conductivity. Layered materials as well as materials with tunnel or channel type structures were selected. Layered materials are of interest as they can provide 2-dimensional ion mobility. Tunnel or channel structures are also of interest as they provide a rigid framework that should remain stable over many discharge/charge cycles. We describe some examples of materials we have synthesized that demonstrate promising electrochemistry.

Takeuchi, Esther Sans [Stony Brook University; Takeuchi, Kenneth James [Stony Brook University; Marschilok, Amy Catherine [Stony Brook University

2013-07-26T23:59:59.000Z

389

UNCLASSIFIED UNCLASSIFIED Nuclear Materials Management & Safeguards...  

National Nuclear Security Administration (NNSA)

UNCLASSIFIED Nuclear Materials Management & Safeguards System CONTACT INFORMATION UPDATE REPORTING IDENTIFICATION SYMBOL (RIS) RIS: Address: Facility Name: CONTACTS Name Email:...

390

Hazardous materials in Aquatic environments of the Mississippi River basin. Quarterly project status report, 1 January 1994--30 March 1994  

SciTech Connect (OSTI)

Projects associated with this grant for studying hazardous materials in aquatic environments of the Mississippi River Basin are reviewed and goals, progress and research results are discussed. New, one-year initiation projects are described briefly.

Abdelghani, A.

1994-06-01T23:59:59.000Z

391

Mechanisms of Plastic and Fracture Instabilities for Alloy Development of Fusion Materials. Final Project Report for period July 15, 1998 - July 14, 2003  

SciTech Connect (OSTI)

The main objective of this research was to develop new computational tools for the simulation and analysis of plasticity and fracture mechanisms of fusion materials, and to assist in planning and assessment of corresponding radiation experiments.

Ghoniem, N. M.

2003-07-14T23:59:59.000Z

392

Exploration of Novel Materials for Development of Next Generation OPV Devices: Cooperative Research and Development Final Report, CRADA Number CRD-10-398  

SciTech Connect (OSTI)

Organic-based solar cells offer the potential for low cost, scalable conversion of solar energy. This project will try to utilize the extensive organic synthetic capabilities of ConocoPhillips to produce novel acceptor and donor materials as well potentially as interface modifiers to produce improved OPV devices with greater efficiency and stability. The synthetic effort will be based on the knowledge base and modeling being done at NREL to identify new candidate materials.

Olson, D.

2012-09-01T23:59:59.000Z

393

High-Performance Corrosion-Resistant Materials: Iron-Based Amorphous-Metal Thermal-Spray Coatings: SAM HPCRM Program ? FY04 Annual Report ? Rev. 0 - DARPA DSO & DOE OCRWM Co-Sponsored Advanced Materials Program  

SciTech Connect (OSTI)

The multi-institutional High Performance Corrosion Resistant Materials (HPCRM) Team is cosponsored by the Defense Advanced Projects Agency (DARPA) Defense Science Office (DSO) and the Department of Energy (DOE) Office of Civilian Radioactive Waste Management (OCRWM), and has developed new corrosion-resistant, iron-based amorphous metals that can be applied as coatings with advanced thermal spray technology. Two compositions have corrosion resistance superior to wrought nickel-based Alloy C-22 (UNS No. N06022) in very aggressive environments, including concentrated calcium-chloride brines at elevated temperature. Corrosion costs the Department of Defense billions of dollars every year, with an immense quantity of material in various structures undergoing corrosion. For example, in addition to fluid and seawater piping, ballast tanks, and propulsions systems, approximately 345 million square feet of structure aboard naval ships and crafts require costly corrosion control measures. The use of advanced corrosion-resistant materials to prevent the continuous degradation of this massive surface area would be extremely beneficial. The Fe-based corrosion-resistant, amorphous-metal coatings under development may prove of importance for applications on ships. Such coatings could be used as an 'integral drip shield' on spent fuel containers, as well as protective coatings that could be applied over welds, thereby preventing exposure to environments that might cause stress corrosion cracking. In the future, such new high-performance iron-based materials could be substituted for more-expensive nickel-based alloys, thereby enabling a reduction in the $58-billion life cycle cost for the long-term storage of the Nation's spent nuclear fuel by tens of percent.

Farmer, J; Haslam, J; Wong, F; Ji, S; Day, S; Branagan, D; Marshall, M; Meacham, B; Buffa, E; Blue, C; Rivard, J; Beardsley, M; Buffa, E; Blue, C; Rivard, J; Beardsley, M; Weaver, D; Aprigliano, L; Kohler, L; Bayles, R; Lemieux, E; Wolejsza, T; Martin, F; Yang, N; Lucadamo, G; Perepezko, J; Hildal, K; Kaufman, L; Heuer, A; Ernst, F; Michal, G; Kahn, H; Lavernia, E

2007-09-19T23:59:59.000Z

394

weapons material  

National Nuclear Security Administration (NNSA)

2%2A en Office of Weapons Material Protection http:nnsa.energy.govaboutusourprogramsnonproliferationprogramofficesinternationalmaterialprotectionandcooperation-1

395

Material Standards for EHS for Engineered Nanoscale Materials Material Standards for  

E-Print Network [OSTI]

#12;#12;Material Standards for EHS for Engineered Nanoscale Materials Material Standards of Standards and Technology, Gaithersburg, MD Workshop Co-Chairs and Principle Report Editors Dianne L. Poster, John A. Small, Michael T. Postek National Institute of Standards and Technology Sponsored by U

Magee, Joseph W.

396

Critical Materials Hub  

Broader source: Energy.gov [DOE]

Critical materials, including some rare earth elements that possess unique magnetic, catalytic, and luminescent properties, are key resources needed to manufacture products for the clean energy economy. These materials are so critical to the technologies that enable wind turbines, solar panels, electric vehicles, and energy-efficient lighting that DOE's 2010 and 2011 Critical Materials Strategy reported that supply challenges for five rare earth metalsdysprosium, neodymium, terbium, europium, and yttriumcould affect clean energy technology deployment in the coming years.1, 2

397

Mobility of Tritium in Engineered and Earth Materials at the NuMI Facility, Fermilab: Progress report for work performed between June 13 and September 30, 2006  

E-Print Network [OSTI]

for the NuMI project, FERMILAB-TM-2009 and NuMI-B-279, Fermito NuMI beam tunnels, FERMILAB-TM-2083, Fermi Nationalprotection radiation safety, Fermilab report, July 2001.

2006-01-01T23:59:59.000Z

398

Identification of Catalysts and Materials for a High-Energy Density Biochemical Fuel Cell: Cooperative Research and Development Final Report, CRADA Number CRD-09-345  

SciTech Connect (OSTI)

The proposed research attempted to identify novel biochemical catalysts, catalyst support materials, high-efficiency electron transfer agents between catalyst active sites and electrodes, and solid-phase electrolytes in order to maximize the current density of biochemical fuel cells that utilize various alcohols as substrates.

Ghirardi, M.; Svedruzic, D.

2013-07-01T23:59:59.000Z

399

Development of New Low-Cost, High-Performance, PV Module Encapsulant/Packaging Materials: Annual Technical Progress Report, Phase 1, 22 October 2002-30 September 2003  

SciTech Connect (OSTI)

The primary objectives of this subcontract are for Specialized Technology Resources, Inc., to work with U.S.-based PV module manufacturers representing crystalline silicon, polycrystalline silicon, amorphous silicon, copper indium diselenide (CIS), and other state-of-the-art thin-film technologies to develop formulations, production processes, prototype and qualify new low-cost, high-performance photovoltaic module encapsulants/packaging materials. The manufacturers will assist in identifying each materials' deficiencies while undergoing development, and then ultimately in qualifying the final optimized materials designed to specifically meet their requirements. Upon completion of this program, new low-cost, high-performance, PV module encapsulant/packaging materials will be qualified, by one or more end-users, for their specific application. Information gathering on topics related to thin-film module technology, including device performance/failure analysis, glass stability, and de vice encapsulation, has been completed. This information has provided concepts and considerations for module failure analysis, accelerated testing design, and encapsulation formulation strategy for thin-film modules.

Agro, S. C.; Tucker, R. T.

2004-03-01T23:59:59.000Z

400

Spent Fuel Working Group report on inventory and storage of the Department`s spent nuclear fuel and other reactor irradiated nuclear materials and their environmental, safety and health vulnerabilities. Volume 2, Working Group Assessment Team reports; Vulnerability development forms; Working group documents  

SciTech Connect (OSTI)

The Secretary of Energy`s memorandum of August 19, 1993, established an initiative for a Department-wide assessment of the vulnerabilities of stored spent nuclear fuel and other reactor irradiated nuclear materials. A Project Plan to accomplish this study was issued on September 20, 1993 by US Department of Energy, Office of Environment, Health and Safety (EH) which established responsibilities for personnel essential to the study. The DOE Spent Fuel Working Group, which was formed for this purpose and produced the Project Plan, will manage the assessment and produce a report for the Secretary by November 20, 1993. This report was prepared by the Working Group Assessment Team assigned to the Hanford Site facilities. Results contained in this report will be reviewed, along with similar reports from all other selected DOE storage sites, by a working group review panel which will assemble the final summary report to the Secretary on spent nuclear fuel storage inventory and vulnerability.

Not Available

1993-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "materials clsm reported" 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

Scintillator material  

DOE Patents [OSTI]

An improved scintillator material comprising cerium fluoride is disclosed. Cerium fluoride has been found to provide a balance of good stopping power, high light yield and short decay constant that is superior to known scintillator materials such as thallium-doped sodium iodide, barium fluoride and bismuth germanate. As a result, cerium fluoride is favorably suited for use as a scintillator material in positron emission tomography. 4 figs.

Anderson, D.F.; Kross, B.J.

1992-07-28T23:59:59.000Z

402

Scintillator material  

DOE Patents [OSTI]

An improved scintillator material comprising cerium fluoride is disclosed. Cerium fluoride has been found to provide a balance of good stopping power, high light yield and short decay constant that is superior to known scintillator materials such as thallium-doped sodium iodide, barium fluoride and bismuth germanate. As a result, cerium fluoride is favorably suited for use as a scintillator material in positron emission tomography. 4 figs.

Anderson, D.F.; Kross, B.J.

1994-06-07T23:59:59.000Z

403

Scintillator material  

DOE Patents [OSTI]

An improved scintillator material comprising cerium fluoride is disclosed. Cerium fluoride has been found to provide a balance of good stopping power, high light yield and short decay constant that is superior to known scintillator materials such as thallium-doped sodium iodide, barium fluoride and bismuth germanate. As a result, cerium fluoride is favorably suited for use as a scintillator material in positron emission tomography.

Anderson, David F. (Batavia, IL); Kross, Brian J. (Aurora, IL)

1992-01-01T23:59:59.000Z

404

Scintillator material  

DOE Patents [OSTI]

An improved scintillator material comprising cerium fluoride is disclosed. Cerium fluoride has been found to provide a balance of good stopping power, high light yield and short decay constant that is superior to known scintillator materials such as thallium-doped sodium iodide, barium fluoride and bismuth germanate. As a result, cerium fluoride is favorably suited for use as a scintillator material in positron emission tomography.

Anderson, David F. (Batavia, IL); Kross, Brian J. (Aurora, IL)

1994-01-01T23:59:59.000Z

405

Critical Materials:  

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

lighting. 14 (bottom) Criticality ratings of shortlisted raw 76 materials. 15 77 2. Technology Assessment and Potential 78 This section reviews the major trends within...

406

BUILDING MATERIALS RECLAMATION PROGRAM  

SciTech Connect (OSTI)

This report describes work conducted on the Building Materials Reclamation Program for the period of September 2008 to August 2010. The goals of the project included selecting materials from the local construction and demolition (C&D) waste stream and developing economically viable reprocessing, reuse or recycling schemes to divert them from landfill storage. Educational resources as well as conceptual designs and engineering feasibility demonstrations were provided for various aspects of the work. The project was divided into two distinct phases: Research and Engineering Feasibility and Dissemination. In the Research Phase, a literature review was initiated and data collection commenced, an advisory panel was organized, and research was conducted to evaluate high volume C&D materials for nontraditional use; five materials were selected for more detailed investigations. In the Engineering Feasibility and Dissemination Phase, a conceptual study for a regional (Mecklenburg and surrounding counties) collection and sorting facility was performed, an engineering feasibility project to demonstrate the viability of recycling or reuse schemes was created, the literature review was extended and completed, and pedagogical materials were developed. Over the two-year duration of the project, all of the tasks and subtasks outlined in the original project proposal have been completed. The Final Progress Report, which briefly describes actual project accomplishments versus the tasks/subtasks of the original project proposal, is included in Appendix A of this report. This report describes the scientific/technical aspects (hypotheses, research/testing, and findings) of six subprojects that investigated five common C&D materials. Table 1 summarizes the six subprojects, including the C&D material studied and the graduate student and the faculty advisor on each subproject.

David C. Weggel; Shen-En Chen; Helene Hilger; Fabien Besnard; Tara Cavalline; Brett Tempest; Adam Alvey; Madeleine Grimmer; Rebecca Turner

2010-08-31T23:59:59.000Z

407

US/French joint research program regarding the behavior of polymer base materials subjected to beta radiation: Volume 2, Phase-2a screening tests: (Final report)  

SciTech Connect (OSTI)

As part of the ongoing joint NRC/CEA cooperative test program to investigate the relative effectiveness of beta and gamma irradiation to produce damage in polymer base materials, ethylene propylene rubber (EPR) specimens, in slab geometry, were exposed to Cobalt-60 gamma rays and accelerator produced electron beams. Specimens were irradiated and evaluated at research facilities in the US (Sandia National Laboratories) and France (Compagnie ORIS Industrie). These tests included several electron beam energies, sample thicknesses, exposure doses, and dose rates. Based on changes in the tensile properties, of the test specimens, results of these studies suggest that material damage resulting from electron and gamma irradiations can be correlated on the basis of absorbed radiation dose.

Buckalew, W.H.; Wyant, F.J.; Chenion, J.; Carlin, F.; Gaussens, G.; Le Tutour, P.; Le Meur, M.

1987-09-01T23:59:59.000Z

408

Final Report on DOE SciDAC project on Next Generation of Multi-Scale Quantum Simulation Software for Strongly Correlated Materials  

SciTech Connect (OSTI)

This report summarizes the accomplishments of the University of California Davis team which is part of a larger SciDAC collaboration including Mark Jarrell of Louisiana State University, Karen Tomko of the Ohio Supercomputer Center, and Eduardo F. D'Azevedo and Thomas A. Maier of Oak Ridge National Laboratory. In this report, we focus on the major UCD accomplishments. As the paper authorship list emphasizes, much of our work is the result of a tightly integrated effort; hence this compendium of UCD efforts of necessity contains some overlap with the work at our partner institutions.

Bai, Zhaojun; Scalettar, Richard; Savrasov, Sergey

2012-07-01T23:59:59.000Z

409

Cermet materials  

DOE Patents [OSTI]

A self-cleaning porous cermet material, filter and system utilizing the same may be used in filtering particulate and gaseous pollutants from internal combustion engines having intermetallic and ceramic phases. The porous cermet filter may be made from a transition metal aluminide phase and an alumina phase. Filler materials may be added to increase the porosity or tailor the catalytic properties of the cermet material. Additionally, the cermet material may be reinforced with fibers or screens. The porous filter may also be electrically conductive so that a current may be passed therethrough to heat the filter during use. Further, a heating element may be incorporated into the porous cermet filter during manufacture. This heating element can be coated with a ceramic material to electrically insulate the heating element. An external heating element may also be provided to heat the cermet filter during use.

Kong, Peter C. (Idaho Falls, ID)

2008-12-23T23:59:59.000Z

410

Evaluation of Alternate Materials for Coated Particle Fuels for the Gas-Cooled Fast Reactor. Laboratory Directed Research and Development Program FY 2006 Final Report  

SciTech Connect (OSTI)

Candidate ceramic materials were studied to determine their suitability as Gas-Cooled Fast Reactor particle fuel coatings. The ceramics examined in this work were: TiC, TiN, ZrC, ZrN, AlN, and SiC. The studies focused on (i) chemical reactivity of the ceramics with fission products palladium and rhodium, (ii) the thermomechanical stresses that develop in the fuel coatings from a variety of causes during burnup, and (iii) the radiation resiliency of the materials. The chemical reactivity of TiC, TiN, ZrC, and ZrN with Pd and Rh were all found to be much lower than that of SiC. A number of important chemical behaviors were observed at the ceramic-metal interfaces, including the formation of specific intermetallic phases and a variation in reaction rates for the different ceramics investigated. Based on the data collected in this work, the nitride ceramics (TiN and ZrN) exhibit chemical behavior that is characterized by lower reaction rates with Pd and Rh than the carbides TiC and ZrC. The thermomechanical stresses in spherical fuel particle ceramic coatings were modeled using finite element analysis, and included contributions from differential thermal expansion, fission gas pressure, fuel kernel swelling, and thermal creep. In general the tangential stresses in the coatings during full reactor operation are tensile, with ZrC showing the lowest values among TiC, ZrC, and SiC (TiN and ZrN were excluded from the comprehensive calculations due to a lack of available materials data). The work has highlighted the fact that thermal creep plays a critical role in the development of the stress state of the coatings by relaxing many of the stresses at high temperatures. To perform ion irradiations of sample materials, an irradiation beamline and high-temperature sample irradiation stage was constructed at the University of Wisconsins 1.7MV Tandem Accelerator Facility. This facility is now capable of irradiating of materials to high dose while controlling sample temperature up to 800C.

Paul A. Demkowicz; Karen Wright; Jian Gan; David Petti; Todd Allen; Jake Blanchard

2006-09-01T23:59:59.000Z

411

Materials Science and Technology Division Light-Water-Reactor Safety Research Program. Quarterly progress report, April-June 1983. Volume 2  

SciTech Connect (OSTI)

The progress report summarizes the Argonne National Laboratory work performed during April, May, and June 1983 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors, Transient Fuel Response and Fission Product Release, Clad Properties for Code Verification, and Long-Term Embrittlement of Cast Duplex Stainless Steels in LWR Systems.

Shack, W.J.

1984-06-01T23:59:59.000Z

412

E-Print Network 3.0 - ashe higher education Sample Search Results  

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

higher abrasion... Center for By-Products Utilization RECENT ADVANCES IN RECYCLING CLEAN- COAL ASH By Tarun R. Naik... -Strength Materials (CLSM); 232, Fly Ash and Natural...

413

E-Print Network 3.0 - ash ahto lobjakas Sample Search Results  

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

Utilization Summary: Center for By-Products Utilization RECENT ADVANCES IN RECYCLING CLEAN- COAL ASH By Tarun R. Naik... -Strength Materials (CLSM); 232, Fly Ash and Natural...

414

E-Print Network 3.0 - ash Sample Search Results  

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

Utilization Summary: Center for By-Products Utilization RECENT ADVANCES IN RECYCLING CLEAN- COAL ASH By Tarun R. Naik... -Strength Materials (CLSM); 232, Fly Ash and Natural...

415

E-Print Network 3.0 - ash paving demonstration Sample Search...  

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

AND DEMONSTRATION... Center for By-Products Utilization RECENT ADVANCES IN RECYCLING CLEAN- COAL ASH By Tarun R. Naik... -Strength Materials (CLSM); 232, Fly Ash and Natural...

416

E-Print Network 3.0 - ash blended cement Sample Search Results  

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

CLSM mixture utilized... . CHARACTERIZATION AND APPLICATION OF CLASS F FLY ASH AND CLEAN-COAL ASH FOR CEMENT-BASED MATERIALS 2 The major... investigation. Two additional ash ......

417

E-Print Network 3.0 - ash penurunan kadar Sample Search Results  

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

Utilization Summary: Center for By-Products Utilization RECENT ADVANCES IN RECYCLING CLEAN- COAL ASH By Tarun R. Naik... -Strength Materials (CLSM); 232, Fly Ash and Natural...

418

E-Print Network 3.0 - ash quarterly technical Sample Search Results  

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

Utilization Summary: Center for By-Products Utilization RECENT ADVANCES IN RECYCLING CLEAN- COAL ASH By Tarun R. Naik... -Strength Materials (CLSM); 232, Fly Ash and Natural...

419

E-Print Network 3.0 - ashes Sample Search Results  

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

Utilization Summary: Center for By-Products Utilization RECENT ADVANCES IN RECYCLING CLEAN- COAL ASH By Tarun R. Naik... -Strength Materials (CLSM); 232, Fly Ash and Natural...

420

E-Print Network 3.0 - ash intranasal instillation Sample Search...  

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

Summary: Center for By-Products Utilization RECENT ADVANCES IN RECYCLING CLEAN- COAL ASH By Tarun R. Naik... -Strength Materials (CLSM); 232, Fly Ash and Natural Pozzolans...

Note: This page contains sample records for the topic "materials clsm reported" 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

Air-Cooled Stack Freeze Tolerance Freeze Failure Modes and Freeze Tolerance Strategies for GenDriveTM Material Handling Application Systems and Stacks Final Scientific Report  

SciTech Connect (OSTI)

Air-cooled stack technology offers the potential for a simpler system architecture (versus liquid-cooled) for applications below 4 kilowatts. The combined cooling and cathode air allows for a reduction in part count and hence a lower cost solution. However, efficient heat rejection challenges escalate as power and ambient temperature increase. For applications in ambient temperatures below freezing, the air-cooled approach has additional challenges associated with not overcooling the fuel cell stack. The focus of this project was freeze tolerance while maintaining all other stack and system requirements. Through this project, Plug Power advanced the state of the art in technology for air-cooled PEM fuel cell stacks and related GenDrive material handling application fuel cell systems. This was accomplished through a collaborative work plan to improve freeze tolerance and mitigate freeze-thaw effect failure modes within innovative material handling equipment fuel cell systems designed for use in freezer forklift applications. Freeze tolerance remains an area where additional research and understanding can help fuel cells to become commercially viable. This project evaluated both stack level and system level solutions to improve fuel cell stack freeze tolerance. At this time, the most cost effective solutions are at the system level. The freeze mitigation strategies developed over the course of this project could be used to drive fuel cell commercialization. The fuel cell system studied in this project was Plug Power's commercially available GenDrive platform providing battery replacement for equipment in the material handling industry. The fuel cell stacks were Ballard's commercially available FCvelocity 9SSL (9SSL) liquid-cooled PEM fuel cell stack and FCvelocity 1020ACS (Mk1020) air-cooled PEM fuel cell stack.

Hancock, David, W.

2012-02-14T23:59:59.000Z

422

Development and characterization of Textron continuous fiber ceramic composite hot gas filter materials. Final report, September 30, 1994--October 31, 1997  

SciTech Connect (OSTI)

Uncertainties about the long-term ability of monolithic ceramics to survive in the IGCC or PFBC hot gas filter environment led DOE/METC to consider the merits of using continuous fiber reinforced ceramic composites (CFCCs) as potential next-generation high temperature filter elements. This seems to be a logical strategy to pursue in light of the fact that properly-engineered CFCC materials have shown much-improved damage tolerance and thermal shock behavior as compared to existing monolithic ceramic materials. Textron`s Advanced Hot Gas Filter Development Program was intended to be a two year, two phase program which transitioned developmental materials R and D into prototype filter element fabrication. The first phase was to demonstrate the technical feasibility of fabricating CFCC hot gas filter elements which could meet the pressure drop specifications of less than ten inches of water (iwg) at a face velocity of ten feet per minute (fpm), while showing sufficient integrity to survive normal mechanical loads and adequate environmental resistance to steam/alkali corrosion conditions at a temperature of approximately 870 C (1600 F). The primary objective of the second phase of the program was to scale up fabrication methods developed in Phase 1 to produce full-scale CFCC candle filters for validation testing. Textron encountered significant process-related and technical difficulties in merely meeting the program permeability specifications, and much effort was expended in showing that this could indeed be achieved. Thus, by the time the Phase 1 program was completed, expenditure of program funds precluded continuing on with Phase 2, and Textron elected to terminate their program after Phase 1. This allowed Textron to be able to focus technical and commercialization efforts on their largely successful DOE CFCC Program.

DiPietro, S.G.; Alvin, M.A.

1997-12-31T23:59:59.000Z

423

Economic Impact of Standard Reference Materials  

E-Print Network [OSTI]

00-1 Planning Report Economic Impact of Standard Reference Materials for Sulfur in Fossil Fuels Administration #12;February 2000 Economic Impact of Standard Reference Materials for Sulfur in Fossil Fuels Final-006 Economic Impact of Standard Reference Materials for Sulfur in Fossil Fuels Final Report February 2000

424

Investigation of test methods, material properties, and processes for solar cell encapsulants. Seventeenth quarterly progress report, May 12-August 12, 1980  

SciTech Connect (OSTI)

The goal of this program is to identify, evaluate, and recommend encapsulant materials and processes for the production of cost-effective, long-life solar cell modules. Development efforts have emphasized the reformulation of polybutyl acrylate, a liquid pottant used in the casting encapsulation process. This material has been modified to yield a composition with much faster cure at lower temperatures. Minimodules have been successfully prepared from this low cost compound and are currently being evaluated by thermal/humidity cycling. Differential thermal analysis (DTA) was used for the examination of thermal stability in some of the pottant compounds of current interest. This method was useful in determining the temperatures at which oxidative or pyrolysis reactions resulted in degradation of the polymers. All the candidate pottants showed degradation onsets of over 200/sup 0/C. The effectiveness of a new primer was determined during this period. This formulation was similar to the silane coupling agent used in past experimentation but was modified with a peroxide to enhance the activity. Excellent bound strengths were obtained to glass, and mild steel that were resistant to immersion in boiling water. EVA to low iron glass gave an average bond strength of 35 lbs per inch of width. This new primer was also evaluated for the corrosion protection that could be provided to metal surfaces when primed and encapsulated in EVA. (WHK)

Willis, P. B.; Baum, B.

1980-09-01T23:59:59.000Z

425

MATE (Materials for Advanced Turbine Engines) Program, Project 3. Volume 2: Design, fabrication and evaluation of an oxide dispersion strengthened sheet alloy combustor liner. Final report  

SciTech Connect (OSTI)

The suitability of wrought oxide dispersion strengthened (ODS) superalloy sheet for gas turbine engine combustor applications was evaluated. Two yttria (Y2O3) dispersion strengthened alloys were evaluated; Incoloy MA956 and Haynes Development Alloy (HDA) 8077 (NiCrAl base). Preliminary tests showed both alloys to be potentially viable combustor materials, with neither alloy exhibiting a significant advantage over the other. MA956 was selected as the final alloy based on manufacturing reproducibility for evaluation as a burner liner. A hybrid PW2037 inner burner liner containing MA956 and Hastelloy X components and using a louvered configuration was designed and constructed. The louvered configuration was chosen because of field experience and compatibility with the bill of material PW2037 design. The simulated flight cycle for the ground based engine tests consisted of 4.5 min idle, 1.5 min takeoff and intermediate conditions in a PW2037 engine with average uncorrected combustor exit temperature of 1527 C. Post test evaluation consisting of visual observations and fluorescent penetrant inspections was conducted after 500 cycles of testing. No loss of integrity in the burner liner was shown.

Bose, S.; Sheffler, K.D.

1988-02-01T23:59:59.000Z

426

Complex Materials  

ScienceCinema (OSTI)

Valentino Cooper uses some of the world's most powerful computing to understand how materials work at subatomic levels, studying breakthroughs such as piezoelectrics, which convert mechanical stress to electrical energy.

Cooper, Valentino

2014-05-23T23:59:59.000Z

427

Complex Materials  

SciTech Connect (OSTI)

Valentino Cooper uses some of the world's most powerful computing to understand how materials work at subatomic levels, studying breakthroughs such as piezoelectrics, which convert mechanical stress to electrical energy.

Cooper, Valentino

2014-04-17T23:59:59.000Z

428

Material Symbols  

E-Print Network [OSTI]

What is the relation between the material, conventional symbol structures that we encounter in the spoken and written word, and human thought? A common assumption, that structures a wide variety of otherwise competing ...

Clark, Andy

2006-01-01T23:59:59.000Z

429

Tulane/Xavier University hazardous materials in aquatic environments of the Mississippi River basin. Quarterly progress report, January 1--March 31, 1996  

SciTech Connect (OSTI)

The objectives of this report are to provide the necessary administrative support to assure that the scientific and educational goals of the project are obtained and to assure that all Department of Energy reporting requirements and requests are fulfilled. The grant reporting is divided into three aspects: Collaborative Cluster projects, Initiation projects and Education projects. A cluster project is one or more closely related collaborative, multidisciplinary research projects in which a group of investigators employs a synergistic approach to the solution of problems in the same general area of research. The accomplishments this quarter of eleven cluster projects are presented. An initial project typically involves a single investigator. The purpose of the project is to undertake pilot work, lasting no more than one year, which will lead to the successful submission of an externally-funded proposal or the development of a collaborative cluster project. The accomplishments this quarter of eleven initiation projects are presented. The education projects are designed to develop courses with emphasis on environmental studies and/or to train students in areas of environmental research.

NONE

1996-05-17T23:59:59.000Z

430

Materials of Gasification  

SciTech Connect (OSTI)

The objective of this project was to accumulate and establish a database of construction materials, coatings, refractory liners, and transitional materials that are appropriate for the hardware and scale-up facilities for atmospheric biomass and coal gasification processes. Cost, fabricability, survivability, contamination, modes of corrosion, failure modes, operational temperatures, strength, and compatibility are all areas of materials science for which relevant data would be appropriate. The goal will be an established expertise of materials for the fossil energy area within WRI. This would be an effort to narrow down the overwhelming array of materials information sources to the relevant set which provides current and accurate data for materials selection for fossil fuels processing plant. A significant amount of reference material on materials has been located, examined and compiled. The report that describes these resources is well under way. The reference material is in many forms including texts, periodicals, websites, software and expert systems. The most important part of the labor is to refine the vast array of available resources to information appropriate in content, size and reliability for the tasks conducted by WRI and its clients within the energy field. A significant has been made to collate and capture the best and most up to date references. The resources of the University of Wyoming have been used extensively as a local and assessable location of information. As such, the distribution of materials within the UW library has been added as a portion of the growing document. Literature from recent journals has been combed for all pertinent references to high temperature energy based applications. Several software packages have been examined for relevance and usefulness towards applications in coal gasification and coal fired plant. Collation of the many located resources has been ongoing. Some web-based resources have been examined.

None

2005-09-15T23:59:59.000Z

431

Materializing Energy  

E-Print Network [OSTI]

Motivated and informed by perspectives on sustainability and design, this paper draws on a diverse body of scholarly works related to energy and materiality to articulate a perspective on energy-as-materiality and propose a design approach of materializing energy. Three critical themes are presented: the intangibility of energy, the undifferentiatedness of energy, and the availability of energy. Each theme is developed through combination of critical investigation and design exploration, including the development and deployment of several novel design artifacts: Energy Mementos and The Local Energy Lamp. A framework for interacting with energy-as-materiality is proposed involving collecting, keeping, sharing, and activating energy. A number of additional concepts are also introduced, such as energy attachment, energy engagement, energy attunement, local energy and energy meta-data. Our work contributes both a broader, more integrative design perspective on energy and materiality as well as a diversity of more specific concepts and artifacts that may be of service to designers and researchers of interactive systems concerned with sustainability and energy. Author Keywords Sustainability, energy, materiality, design, design theory

James Pierce; Eric Paulos

432

Fissile Material Disposition Program: Deep Borehole Disposal Facility PEIS data input report for direct disposal. Direct disposal of plutonium metal/plutonium dioxide in compound metal canisters. Version 3.0  

SciTech Connect (OSTI)

The US Department of Energy (DOE) is examining options for disposing of excess weapons-usable nuclear materials [principally plutonium (Pu) and highly enriched uranium (HEU)] in a form or condition that is substantially and inherently more difficult to recover and reuse in weapons production. This report is the data input report for the Programmatic Environmental Impact Statement (PEIS). The PEIS examines the environmental, safety, and health impacts of implementing each disposition alternative on land use, facility operations, and site infrastructure; air quality and noise; water, geology, and soils; biotic, cultural, and paleontological resources; socioeconomics; human health; normal operations and facility accidents; waste management; and transportation. This data report is prepared to assist in estimating the environmental effects associated with the construction and operation of a Deep Borehole Disposal Facility, an alternative currently included in the PEIS. The facility projects under consideration are, not site specific. This report therefore concentrates on environmental, safety, and health impacts at a generic site appropriate for siting a Deep Borehole Disposal Facility.

Wijesinghe, A.M.; Shaffer, R.J.

1996-01-15T23:59:59.000Z

433

Material Analysis for a Fire Assessment.  

SciTech Connect (OSTI)

This report consolidates technical information on several materials and material classes for a fire assessment. The materials include three polymeric materials, wood, and hydraulic oil. The polymers are polystyrene, polyurethane, and melamine- formaldehyde foams. Samples of two of the specific materials were tested for their behavior in a fire - like environment. Test data and the methods used to test the materials are presented. Much of the remaining data are taken from a literature survey. This report serves as a reference source of properties necessary to predict the behavior of these materials in a fire.

Brown, Alexander; Nemer, Martin

2014-08-01T23:59:59.000Z

434

Summary Report for Concentrating Solar Power Thermal Storage Workshop: New Concepts and Materials for Thermal Energy Storage and Heat-Transfer Fluids, May 20, 2011  

SciTech Connect (OSTI)

This document summarizes a workshop on thermal energy storage for concentrating solar power (CSP) that was held in Golden, Colorado, on May 20, 2011. The event was hosted by the U.S. Department of Energy (DOE), the National Renewable Energy Laboratory, and Sandia National Laboratories. The objective was to engage the university and laboratory research communities to identify and define research directions for developing new high-temperature materials and systems that advance thermal energy storage for CSP technologies. This workshop was motivated, in part, by the DOE SunShot Initiative, which sets a very aggressive cost goal for CSP technologies -- a levelized cost of energy of 6 cents per kilowatt-hour by 2020 with no incentives or credits.

Glatzmaier, G.

2011-08-01T23:59:59.000Z

435

Oak Ridge Health Studies Phase 1 report, Volume 2: Part D, Dose Reconstruction Feasibility Study. Tasks 6, Hazard summaries for important materials at the Oak Ridge Reservation  

SciTech Connect (OSTI)

The purpose of Task 6 of Oak Ridge Phase I Health Studies is to provide summaries of current knowledge of toxic and hazardous properties of materials that are important for the Oak Ridge Reservation. The information gathered in the course of Task 6 investigations will support the task of focussing any future health studies efforts on those operations and emissions which have likely been most significant in terms of off-site health risk. The information gathered in Task 6 efforts will likely also be of value to individuals evaluating the feasibility of additional health,study efforts (such as epidemiological investigations) in the Oak Ridge area and as a resource for citizens seeking information on historical emissions.

Bruce, G.M.; Walker, L.B.; Widner, T.E.

1993-09-01T23:59:59.000Z

436

FY-05 First Quarter Report on Development of a Supercritical Carbon Dioxide Brayton Cycle: Improving PBR Efficiency and Testing Material Compatibility  

SciTech Connect (OSTI)

The objective of this research is to improve a helium Brayton cycle and to develop a supercritical carbon dioxide Brayton cycle for the Pebble Bed Reactor (PBR) that can also be applied to the Fast Gas-Cooled Reactor (FGR) and the Very-High-Temperature Gas- Cooled Reactor (VHTR). The proposed supercritical carbon dioxide Brayton cycle will be used to improve the PBR, FGR, and VHTR net plant efficiency. Another objective of this research is to test materials to be used in the power conversion side at supercritical carbon dioxide conditions. Generally, the optimized Brayton cycle and balance of plant (BOP) to be developed from this study can be applied to Generation-IV reactor concepts. Particularly, we are interested in VHTR because it has a good chance of being built in the near future.

Chang Oh

2005-01-01T23:59:59.000Z

437

Properties of yttria-tetragonal zirconia polycrystal (Y-TZP) materials after long-term exposure to elevated temperatures. Final report  

SciTech Connect (OSTI)

Seven commercially available yttria-tetragonal zirconia polycrystal (Y-TZP) materials were evaluated. Room temperature properties were measured before and after heat treatments at 1000C. Microstructure and phase stability were also examined. In all but one case, the Y-TZPs showed very little change in room temperature properties after long times at this temperature. Results show that pressure-assisted processing greatly improves the strength by reducing porosity and keeping the grain size extremely fine, but this reduces the toughness because finer grains are more difficult to transform. In addition, a small amount of cubic zirconia appears to enhance the toughness of fine-grained Y-TZP while maintaining good strength. During processing, a small amount of cubic zirconia is formed and allowed to grow. This creates regions poor in yttria which can transform spontaneously in the presence of a crack-tip stress field.

Swab, J.J. [Army Materials Research Agency, Watertown, MA (United States). Materials Technology Lab.

1989-03-01T23:59:59.000Z

438

Mobility of Tritium in Engineered and Earth Materials at the NuMIFacility, Fermilab: Progress report for work performed between June 13and September 30, 2006  

SciTech Connect (OSTI)

This report details the work done between June 13 andSeptember 30, 2006 by Lawrence Berkeley National Laboratory (LBNL)scientists to assist Fermi National Accelerator Laboratory (Fermilab)staff in understanding tritium transport at the Neutrino at the MainInjector (NuMI) facility. As a byproduct of beamline operation, thefacility produces (among other components) tritium in engineeredmaterials and the surrounding rock formation. Once the tritium isgenerated, it may be contained at the source location, migrate to otherregions within the facility, or be released to theenvironment.

Pruess, Karsten; Conrad, Mark; Finsterle, Stefan; Kennedy, Mack; Kneafsey, Timothy; Salve, Rohit; Su, Grace; Zhou, Quanlin

2006-10-25T23:59:59.000Z

439

Energy Materials Coordinating Committee (EMaCC)  

SciTech Connect (OSTI)

This report summarizes EMaCC activities for fiscal year 1990 and describes the materials research programs of various offices and divisions within the department. The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further the effective use of materials expertise within the department. (JL)

Not Available

1991-05-31T23:59:59.000Z

440

Final Safety Evaluation Report to license the construction and operation of a facility to receive, store, and dispose of 11e.(2) byproduct material near Clive, Utah (Docket No. 40-8989)  

SciTech Connect (OSTI)

The Final Safety Evaluation Report (FSER) summarizes the US Nuclear Regulatory Commission (NRC) staff`s review of Envirocare of Utah, Inc.`s (Envirocare`s) application for a license to receive, store, and dispose of uranium and thorium byproduct material (as defined in Section 11e.(2) of the Atomic Energy Act of 1954, as amended) at a site near Clive, Utah. Envirocare proposes to dispose of high-volume, low-activity Section 11e.(2) byproduct material in separate earthen disposal cells on a site where the applicant currently disposes of naturally occurring radioactive material (NORM), low-level waste, and mixed waste under license by the Utah Department of Environmental Quality. The NRC staff review of the December 23, 1991, license application, as revised by page changes dated July 2 and August 10, 1992, April 5, 7, and 10, 1993, and May 3, 6, 7, 11, and 21, 1993, has identified open issues in geotechnical engineering, water resources protection, radon attenuation, financial assurance, and radiological safety. The NRC will not issue a license for the proposed action until Envirocare adequately resolves these open issues.

Not Available

1994-01-01T23:59:59.000Z

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


441

Hardfacing material  

DOE Patents [OSTI]

A method of producing a hard metallic material by forming a mixture containing at least 55% iron and at least one of boron, carbon, silicon and phosphorus. The mixture is formed into an alloy and cooled to form a metallic material having a hardness of greater than about 9.2 GPa. The invention includes a method of forming a wire by combining a metal strip and a powder. The metal strip and the powder are rolled to form a wire containing at least 55% iron and from two to seven additional elements including at least one of C, Si and B. The invention also includes a method of forming a hardened surface on a substrate by processing a solid mass to form a powder, applying the powder to a surface to form a layer containing metallic glass, and converting the glass to a crystalline material having a nanocrystalline grain size.

Branagan, Daniel J. (Iona, ID)

2012-01-17T23:59:59.000Z

442

[Technology transfer of building materials by ECOMAT  

SciTech Connect (OSTI)

This report discusses the plan for technology transfer of building materials developed by ECOMAT to the commercial private sector. Some of the materials are briefly discussed like foams, fiber reinforcement, fly ash development, and polymer fillers.

NONE

1996-01-01T23:59:59.000Z

443

Highly Enriched Uranium Materials Facility, Major Design Changes...  

Energy Savers [EERE]

Highly Enriched Uranium Materials Facility, Major Design Changes Late...Lessons Learned Report, NNSA, Dec 2010 Highly Enriched Uranium Materials Facility, Major Design Change