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1

Nonproliferation and arms control assessment of weapons-usable fissile material storage and excess plutonium disposition alternatives  

SciTech Connect (OSTI)

This report has been prepared by the Department of Energy`s Office of Arms Control and Nonproliferation (DOE-NN) with support from the Office of Fissile Materials Disposition (DOE-MD). Its purpose is to analyze the nonproliferation and arms reduction implications of the alternatives for storage of plutonium and HEU, and disposition of excess plutonium, to aid policymakers and the public in making final decisions. While this assessment describes the benefits and risks associated with each option, it does not attempt to rank order the options or choose which ones are best. It does, however, identify steps which could maximize the benefits and mitigate any vulnerabilities of the various alternatives under consideration.

NONE

1997-01-01T23:59:59.000Z

2

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

3

EIS-0229: Storage and Disposition of Weapons-Usable Fissile Materials  

Broader source: Energy.gov [DOE]

The EIS will evaluate thereasonable alternatives and potential environmental impacts for the proposed siting, construction, and operation of three types of facilities for plutonium disposition.

4

Fissile material disposition program final immobilization form assessment and recommendation  

SciTech Connect (OSTI)

Lawrence Livermore National Laboratory (LLNL), in its role as the lead laboratory for the development of plutonium immobilization technologies for the Department of Energy`s Office of Fissile Materials Disposition (MD), has been requested by MD to recommend an immobilization technology for the disposition of surplus weapons- usable plutonium. The recommendation and supporting documentation was requested to be provided by September 1, 1997. This report addresses the choice between glass and ceramic technologies for immobilizing plutonium using the can-in-canister approach. Its purpose is to provide a comparative evaluation of the two candidate technologies and to recommend a form based on technical considerations.

Cochran, S.G.; Dunlop, W.H.; Edmunds, T.A.; MacLean, L.M.; Gould, T.H. [Westinghouse Savannah River Co., Aiken, SC (United States)

1997-10-03T23:59:59.000Z

5

Fissile material detector  

DOE Patents [OSTI]

A detector for fissile materials which provides for integrity monitoring of fissile materials and can be used for nondestructive assay to confirm the presence of a stable content of fissile material in items. The detector has a sample cavity large enough to enable assay of large items of arbitrary configuration, utilizes neutron sources fabricated in spatially extended shapes mounted on the endcaps of the sample cavity, incorporates a thermal neutron filter insert with reflector properties, and the electronics module includes a neutron multiplicity coincidence counter.

Ivanov, Alexander I. (Dubna, RU); Lushchikov, Vladislav I. (Dubna, RU); Shabalin, Eugeny P. (Dubna, RU); Maznyy, Nikita G. (Dubna, RU); Khvastunov, Michael M. (Dubna, RU); Rowland, Mark (Alamo, CA)

2002-01-01T23:59:59.000Z

6

Fissile Materials Disposition | National Nuclear Security Administrati...  

National Nuclear Security Administration (NNSA)

uranium have become surplus to the defense needs of both the United States and Russia. The Office of Fissile Materials Disposition (FMD) plays an important role in...

7

Recovery of fissile materials from plutonium residues, miscellaneous spent nuclear fuel, and uranium fissile wastes  

SciTech Connect (OSTI)

A new process is proposed that converts complex feeds containing fissile materials into a chemical form that allows the use of existing technologies (such as PUREX and ion exchange) to recover the fissile materials and convert the resultant wastes to glass. Potential feed materials include (1) plutonium scrap and residue, (2) miscellaneous spent nuclear fuel, and (3) uranium fissile wastes. The initial feed materials may contain mixtures of metals, ceramics, amorphous solids, halides, and organics. 14 refs., 4 figs.

Forsberg, C.W.

1997-03-01T23:59:59.000Z

8

Shipping container for fissile material  

DOE Patents [OSTI]

The present invention is directed to a shipping container for the interstate transportation of enriched uranium materials. The shipping container is comprised of a rigid, high-strength, cylindrical-shaped outer vessel lined with thermal insulation. Disposed inside the thermal insulation and spaced apart from the inner walls of the outer vessel is a rigid, high-strength, cylindrical inner vessel impervious to liquid and gaseous substances and having the inner surfaces coated with a layer of cadmium to prevent nuclear criticality. The cadmium is, in turn, lined with a protective shield of high-density urethane for corrosion and wear protection. 2 figs.

Crowder, H.E.

1984-12-17T23:59:59.000Z

9

Recovery of fissile materials from nuclear wastes  

DOE Patents [OSTI]

A process for recovering fissile materials such as uranium, and plutonium, and rare earth elements, from complex waste feed material, and converting the remaining wastes into a waste glass suitable for storage or disposal. The waste feed is mixed with a dissolution glass formed of lead oxide and boron oxide resulting in oxidation, dehalogenation, and dissolution of metal oxides. Carbon is added to remove lead oxide, and a boron oxide fusion melt is produced. The fusion melt is essentially devoid of organic materials and halogens, and is easily and rapidly dissolved in nitric acid. After dissolution, uranium, plutonium and rare earth elements are separated from the acid and recovered by processes such as PUREX or ion exchange. The remaining acid waste stream is vitrified to produce a waste glass suitable for storage or disposal. Potential waste feed materials include plutonium scrap and residue, miscellaneous spent nuclear fuel, and uranium fissile wastes. The initial feed materials may contain mixtures of metals, ceramics, amorphous solids, halides, organic material and other carbon-containing material.

Forsberg, Charles W. (Oak Ridge, TN)

1999-01-01T23:59:59.000Z

10

Proliferation resistance criteria for fissile material disposition  

SciTech Connect (OSTI)

The 1994 National Academy of Sciences study {open_quotes}Management and Disposition of Excess Weapons Plutonium{close_quotes} defined options for reducing the national and international proliferation risks of materials declared excess to the nuclear weapons program. This report proposes criteria for assessing the proliferation resistance of these options. The criteria are general, encompassing all stages of the disposition process from storage through intermediate processing to final disposition including the facilities, processing technologies and materials, the level of safeguards for these materials, and the national/subnational threat to the materials.

Close, D.A.; Fearey, B.L.; Markin, J.T.; Rutherford, D.A. [Los Alamos National Lab., NM (United States); Duggan, R.A.; Jaeger, C.D.; Mangan, D.L.; Moya, R.W.; Moore, L.R. [Sandia National Labs., Albuquerque, NM (United States); Strait, R.S. [Lawrence Livermore National Lab., CA (United States)

1995-04-01T23:59:59.000Z

11

Fissile material storage in the Oak Ridge Radiochemical Development Facility  

SciTech Connect (OSTI)

As a part of a Department of Energy review of Oak Ridge National Laboratory facilities, nuclear safety documentation for the Radiochemical Development Facility (Building 3019) was found to be inadequate. While calculations existed which established safe limits for the storage of fissile material, these calculations were not performed with verified/validated software nor were the results reported in the manner prescribed by applicable DOE orders and ORNL procedures. To address this deficiency, the operations conducted in Building 3019 were reviewed and conditions were compared to available critical experiment data. Applicable critical experiments were selected and multiplication factors were calculated. Subcritical limits were derived for each of three fissile materials (U-233, U-235, and Pu-239). One application of these limits was to certify the safety of a storage array which could contain any or all of the above nuclides at varying degrees of moderation. The studies presented are believed to fulfill most of the applicable regulatory requirements.

Primm, R.T. III

1993-08-01T23:59:59.000Z

12

DISSOLUTION OF FISSILE MATERIALS CONTAINING TANTALUM METAL  

SciTech Connect (OSTI)

The dissolution of composite materials containing plutonium (Pu) and tantalum (Ta) metals is currently performed in Phase I of the HB-Line facility. The conditions for the present flowsheet are the dissolution of 500 g of Pu metal in the 15 L dissolver using a 4 M nitric acid (HNO{sub 3}) solution containing 0.2 M potassium fluoride (KF) at 95 C for 4-6 h.[1] The Ta metal, which is essentially insoluble in HNO{sub 3}/fluoride solutions, is rinsed with process water to remove residual acid, and then burned to destroy classified information. During the initial dissolution campaign, the total mass of Pu and Ta in the dissolver charge was limited to nominally 300 g. The reduced amount of Pu in the dissolver charge coupled with significant evaporation of solution during processing of several dissolver charges resulted in the precipitation of a fluoride salt contain Pu. Dissolution of the salt required the addition of aluminum nitrate (Al(NO{sub 3}){sub 3}) and a subsequent undesired 4 h heating cycle. As a result of this issue, HB-Line Engineering requested the Savannah River National Laboratory (SRNL) to optimize the dissolution flowsheet to reduce the cycle time, reduce the risk of precipitating solids, and obtain hydrogen (H{sub 2}) generation data at lower fluoride concentrations.[2] Using samples of the Pu/Ta composite material, we performed three experiments to demonstrate the dissolution of the Pu metal using HNO{sub 3} solutions containing 0.15 and 0.175 M KF. When 0.15 M KF was used in the dissolving solution, 95.5% of the Pu in the sample dissolved in approximately 6 h. The undissolved material included a small amount of Pu metal and plutonium oxide (PuO{sub 2}) solids. Complete dissolution of the metal would have likely occurred if the dissolution time had been extended. This assumption is based on the steady increase in the Pu concentration observed during the last several hours of the experiment. We attribute the formation of PuO{sub 2} to the complexation of fluoride by the Pu. The fluoride became unavailable to catalyze the dissolution of PuO{sub 2} as it formed on the surface of the metal. The mass of Pu dissolved is equivalent to the dissolution of 343 g of Pu in the HB-Line dissolvers. In the initial experiment with 0.175 M KF in the solution, we achieved complete dissolution of the Pu in 6 h. The mass of Pu dissolved scales to the dissolution of 358 g of Pu in the HB-Line dissolvers. The second experiment using 0.175 M KF was terminated after approximately 6 h following the dissolution of 92.7% of the Pu in the sample; however, dissolution of additional Pu was severely limited due to the slow dissolution rate observed beyond approximately 4 h. A small amount of PuO{sub 2} was also produced in the solution. The slow rate of dissolution was attributed to the diminishing surface area of the Pu and a reduction in the fluoride activity due to complexation with Pu. Given time (>4 h), the Pu metal may have dissolved using the original solution or a significant portion may have oxidized to PuO{sub 2}. If the metal oxidized to PuO{sub 2}, we expect little of the material would have dissolved due to the fluoride complexation and the low HNO{sub 3} concentration. The mass of Pu dissolved in the second experiment scales to the dissolution of 309 g of Pu in the HB-Line dissolvers. Based on the data from the Pu/Ta dissolution experiments we recommend the use of 4 M HNO{sub 3} containing 0.175 M KF for the dissolution of 300 g of Pu metal in the 15 L HB-Line dissolver. A dissolution temperature of nominally 95 C should allow for essentially complete dissolution of the metal in 6 h. Although the H{sub 2} concentration in the offgas from the experiments was at or below the detection limit of the gas chromatograph (GC) used in these experiments, small concentrations (<3 vol %) of H{sub 2} are typically produced in the offgas during Pu metal dissolutions. Therefore, appropriate controls must be established to address the small H{sub 3} generation rates in accordance with this work and the earlier flowsheet demonstrated

Rudisill, T; Mark Crowder, M; Michael Bronikowski, M

2007-05-29T23:59:59.000Z

13

A system for the detection of concealed nuclear weapons and fissile material aboard cargo cotainerships  

E-Print Network [OSTI]

A new approach to the detection of concealed nuclear weapons and fissile material aboard cargo containerships is proposed. The ship-based approach removes the constraints of current thinking by addressing the threat of ...

Gallagher, Shawn P., S.M. Massachusetts Institute of Technology

2005-01-01T23:59:59.000Z

14

Implementation of safeguards and security for fissile materials disposition reactor alternative facilities  

SciTech Connect (OSTI)

A number of different disposition alternatives are being considered and include facilities which provide for long-ten-n and interim storage, convert and stabilize fissile materials for other disposition alternatives, immobilize fissile material in glass and/or ceramic material, fabricate fissile material into mixed oxide (MOX) fuel for reactors, use reactor based technologies to convert material into spent fuel, and dispose of fissile material using a number of geologic alternatives. Particular attention will be given to the reactor alternatives which include existing, partially completed, advanced or evolutionary LWRs and CANDU reactors. The various reactor alternatives are all very similar and include processing which converts Pu to a usable form for fuel fabrication, a MOX fuel fab facility located in either the US or in Europe, US LWRs or the CANDU reactors and ultimate disposal of spent fuel in a geologic repository. This paper focuses on how the objectives of reducing security risks and strengthening arms reduction and nonproliferation will be accomplished and the possible impacts of meeting these objectives on facility operations and design. Some of the areas in this paper include: (1) domestic and international safeguards requirements, (2) non-proliferation criteria and measures, (3) the threat, and (4) potential proliferation risks, the impacts on the facilities, and safeguards and security issues unique to the presence of Category 1 or strategic special nuclear material.

Jaeger, C.D.; Duggan, R.A.; Tolk, K.M.

1995-10-01T23:59:59.000Z

15

An active system for the detection of special fissile material in small watercraft  

E-Print Network [OSTI]

technique. The MCNP Monte Carlo transport code was used to simulate the use of a pulsed neutron generator to induce fission in the fissile material and then estimate the detector response. The detector modeled was based on elastic scattering-induced recoil...

Johansen, Norman Alfan, III

2006-10-30T23:59:59.000Z

16

Proliferation resistance criteria for fissile material disposition issues  

SciTech Connect (OSTI)

The 1994 National Acdaemy of Sciences study ``Management and Disposition of Excess Weapons Plutonium`` defined options for reducing the national and international proliferation risks of materials declared excess to the nuclear weapons program. This paper proposes criteria for assessing the proliferation resistance of these options as well defining the ``Standards`` from the report. The criteria are general, encompassing all stages of the disposition process from storage through intermediate processing to final disposition including the facilities, processing technologies and materials, the level of safeguards for these materials, and the national/subnational threat to the materials.

Rutherford, D.A.; Fearey, B.L.; Markin, J.T.; Close, D.A. [Los Alamos National Lab., NM (United States); Tolk, K.M.; Mangan, D.L. [Sandia National Labs., Albuquerque, NM (United States); Moore, L. [Lawrence Livermore National Lab., CA (United States)

1995-09-01T23:59:59.000Z

17

Processing fissile material mixtures containing zirconium and/or carbon  

DOE Patents [OSTI]

A method of processing spent TRIZO-coated nuclear fuel may include adding fluoride to complex zirconium present in a dissolved TRIZO-coated fuel. Complexing the zirconium with fluoride may reduce or eliminate the potential for zirconium to interfere with the extraction of uranium and/or transuranics from fission materials in the spent nuclear fuel.

Johnson, Michael Ernest; Maloney, Martin David

2013-07-02T23:59:59.000Z

18

Criticality safety analysis on fissile materials in Fukushima reactor cores  

SciTech Connect (OSTI)

The present study focuses on the criticality analysis for geological disposal of damaged fuels from Fukushima reactor cores. Starting from the basic understanding of behaviors of plutonium and uranium, a scenario sequence for criticality event is considered. Due to the different mobility of plutonium and uranium in geological formations, the criticality safety is considered in two parts: (1) near-field plutonium system and (2) far-field low enriched uranium (LEU) system. For the near-field plutonium system, a mathematical analysis for pure-solute transport was given, assuming a particular buffer material and waste form configuration. With the transport and decay of plutonium accounted, the critical mass of plutonium was compared with the initial load of a single canister. Our calculation leads us to the conclusion that our system with the initial loading being the average mass of plutonium in an assembly just before the accident is very unlikely to become critical over time. For the far-field LEU system, due to the uncertainties in the geological and geochemical conditions, calculations were made in a parametric space that covers the variation of material compositions and different geometries. Results show that the LEU system could not remain sub-critical within the entire parameter space assumed, although in the iron-rich rock, the neutron multiplicity is significantly reduced.

Liu, Xudong; Lemaitre-Xavier, E.; Ahn, Joonhong [Department of Nuclear Engineering, University of California, Berkeley, Berkeley, CA 94720 (United States); Hirano, Fumio [Japan Atomic Energy Agency, Geological Isolation Research and Development Directorate, Tokai-mura, Ibaraki 319-1194 (Japan)

2013-07-01T23:59:59.000Z

19

Separation and Quantification of Chemically Diverse Analytes in Neutron Irradiated Fissile Materials  

SciTech Connect (OSTI)

Quantitative measurement of fission and activation products resulting from neutron irradiation of fissile materials is of interest for applications in environmental monitoring, nuclear waste management, and national security. To overcome mass and spectral interferences, and the relative small quantities of some target analytes, an extensive series of chemical separations is necessary. Based on established separations processes involving co-precipitation, solvent extraction, and ion-exchange and extraction chromatography, we have been evaluating and optimizing a proposed sequence of separation steps to allow for the timely quantification of analytes of interest. For simplicity, much of the chemical separation development work has been performed using stable elements as surrogates for the radioactive material. We have recently evaluated the optimized procedures using an irradiated sample to examine the adequacy of separations for measurement of desired analytes by gamma spectrometry. Here we present the results of this evaluation and describe the radiochemical separations utilized.

Douglas, Matthew; Friese, Judah I.; Greenwood, Lawrence R.; Farmer, Orville T.; Thomas, Linda MP; Maiti, Tapas C.; Finn, Erin C.; Garofoli, Stephanie J.; Gassman, Paul L.; Huff, Morgan M.; Schulte, Shannon M.; Smith, Steven C.; Thomas, Kathie K.; Bachelor, Paula P.

2009-10-01T23:59:59.000Z

20

Fissile solution measurement apparatus  

DOE Patents [OSTI]

An apparatus for determining the content of a fissile material within a solution by detecting delayed fission neutrons emitted by the fissile material after it is temporarily irradiated by a neutron source. The apparatus comprises a container holding the solution and having a portion defining a neutron source cavity centrally disposed within the container. The neutron source cavity temporarily receives the neutron source. The container has portions defining a plurality of neutron detector ports that form an annular pattern and surround the neutron source cavity. A plurality of neutron detectors count delayed fission neutrons emitted by the fissile material. Each neutron detector is located in a separate one of the neutron detector ports.

Crane, T.W.; Collinsworth, P.R.

1984-06-11T23:59:59.000Z

Note: This page contains sample records for the topic "weapons-usable fissile materials" 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

THE EFFECT OF INCREASING TEMPERATURE ON K-EFF FOR FISSILE MATERIAL OUTSIDE REACTORS  

SciTech Connect (OSTI)

Nuclear Criticality Safety Evaluations typically employ room temperature cross sections, material densities, and dimensions. Processes that have been and are in development for conversion of legacy wastes in tanks, e.g., Waste Treatment Project (WTP) at the Hanford Remediation Site and Defense Waste Processing Facility (DWPF) at the Savannah River Site, utilize melters that operate at elevated temperatures, 1500 to 1900 C. The applicability of room temperature data to processes such as these has been questioned. Also questioned was the applicability of room temperature data for the analyses across the Savannah River Site (SRS) where the temperature may be elevated, such as in a postulated fire. This analysis was performed to examine the effect of temperature over the relatively small range encountered in normal and abnormal operations at SRS that does not include DWPF melters. This analysis documented herein is limited to fast systems of fissile metal and oxide cylinders on concrete at temperatures no greater than 640 C, the melting point of plutonium. Because thermal expansion data for various types of structural materials was not readily available, structural materials were not included in the analysis.

Kessler, S.

2009-06-09T23:59:59.000Z

22

Nondestructive assay (NDA) of fissile material solutions in tanks at Rocky Flats Environmental Technology Site  

SciTech Connect (OSTI)

Nondestructive assay of holdup in solution tanks at Rocky Flats has been performed to address criticality safety concerns since 1974. Destructive analysis techniques were used for quantification of the fissile material content of the tanks. With termination of operations in 1989, including sparging and sampling of tanks, a need arose for nondestructive assay of solutions in tanks to confirm previous inventory values. Gamma ray measurement methodologies were investigated and several techniques, including Poor Man`s Densitometry were implemented. These techniques have been applied to several different types of tanks including: annular, raschig ring filled, and pencil tanks. For the annular tanks ``Poor Man`s Densitometry`` is used, with the densities of the measured solutions normalized to the value of one ``accepted`` concentration tank. Measurement uncertainties for this technique has been better than was anticipated. Measurements are also performed at several levels to attempt to detect variations in density. For the current tank draining program, solution in tanks is assayed by the NDA gamma-ray technique before draining. Measurement results were obtained for plutonium, uranium, and mixtures of U/Pu solutions for concentrations ranging from less than 0.5 g/l to 150 g/l. Tanks with expected concentrations were used to establish a relationship between concentration and count rate. ``Bootstrapping`` calibration techniques were used in some cases to obtain quantitative results.

Fleissner, J.G.; Lamb, F.W.; Maul, M.R.

1995-07-01T23:59:59.000Z

23

Opportunities exist for the diversion of weapons-usable material at the front end of the fuel cycle, during which  

E-Print Network [OSTI]

, North Korea, Pakistan, and South Africa. (South Africa abandoned its nuclear weapons in 1991. Libya of setting up its own enrichment or spent-fuel treat- ment facilities is enormous. Countries with a new

Laughlin, Robert B.

24

Productivity Techniques and Quality Aspects in the Criticality Safety Evaluation of Y-12 Type-B Fissile Material Packages  

SciTech Connect (OSTI)

The inventory of certified Type-B fissile material packages consists of ten performance-based packages for offsite transportation purposes, serving transportation programs at the Y-12 National Security Complex. The containment vessels range from 5 to 19 in. in diameter and from 17 to 58 in. in height. The drum assembly external to the containment vessel ranges from 18 to 34 in. in diameter and from 26 to 71 in. in height. The weight of the packaging (drum assembly and containment vessel) ranges from 239 to 1550 lb. The older DT-nn series of Cellotex-based packages are being phased-out and replaced by a new generation of Kaolite-based ('Y-12 patented insulation') packages capable of withstanding the dynamic crush test 10 CFR 71.73(c)(2). Three replacement packages are in various stages of development; two are in use. The U.S. Department of Transportation (DOT) 6M specification package, which does not conform to the U.S. Nuclear Regulatory Commission requirements for Type-B packages, is no longer authorized for service on public roads. The ES-3100 shipping package is an example of a Kaolite-based Type-B fissile material package developed as a replacement package for the DOT 6M. With expanded utility, the ES-3100 is designed and licensed for transporting highly enriched uranium and plutonium materials on public roads. The ES-3100 provides added capability for air transport of up to 7-kg quantities of uranium material. This paper presents the productivity techniques and quality aspects in the criticality safety evaluation of Y-12 packages using the ES-3100 as an example.

DeClue, J. F.

2011-06-28T23:59:59.000Z

25

FATE OF FISSILE MATERIAL BOUND TO MONOSODIUM TITANATE DURING COOPER CATALYZED PEROXIDE OXIDATION OF TANK 48H WASTE  

SciTech Connect (OSTI)

At the Savannah River Site (SRS), Tank 48H currently holds approximately 240,000 gallons of slurry which contains potassium and cesium tetraphenylborate (TPB). A copper catalyzed peroxide oxidation (CCPO) reaction is currently being examined as a method for destroying the TPB present in Tank 48H. Part of the development of that process includes an examination of the fate of the Tank 48H fissile material which is adsorbed onto monosodium titanate (MST) particles. This report details results from experiments designed to examine the potential degradation of MST during CCPO processing and the subsequent fate of the adsorbed fissile material. Experiments were conducted to simulate the CCPO process on MST solids loaded with sorbates in a simplified Tank 48H simulant. Loaded MST solids were placed into the Tank 48H simplified simulant without TPB, and the experiments were then carried through acid addition (pH adjustment to 11), peroxide addition, holding at temperature (50 C) for one week, and finally NaOH addition to bring the free hydroxide concentration to a target concentration of 1 M. Testing was conducted without TPB to show the maximum possible impact on MST since the competing oxidation of TPB with peroxide was absent. In addition, the Cu catalyst was also omitted, which will maximize the interaction of H{sub 2}O{sub 2} with the MST; however, the results may be non-conservative assuming the Cu-peroxide active intermediate is more reactive than the peroxide radical itself. The study found that both U and Pu desorb from the MST when the peroxide addition begins, although to different extents. Virtually all of the U goes into solution at the beginning of the peroxide addition, whereas Pu reaches a maximum of {approx}34% leached during the peroxide addition. Ti from the MST was also found to come into solution during the peroxide addition. Therefore, Ti is present with the fissile in solution. After the peroxide addition is complete, the Pu and Ti are found to precipitate from solution, while the U remains in solution throughout the remaining processes, including pH adjustment to 1 M free hydroxide. The Ti is likely forming a peroxotitanate material, which can then resorb the leached Pu from solution, but has a low affinity for U. Since Pu was not detected in the SEMEDS studies, it cannot be conclusively determined in what form the Pu returns to the solids; however, the Pu likely resorbed onto the peroxotitanate material. Based on the results of this experiment, Savannah River National Laboratory (SRNL) recommends the following experiments to further examine the fate of fissile material in CCPO processing of Tank 48H: (1) Repeat with full simulant matrix (organic and Cu catalyst present along with simulated radioactive sludge); and (2) Repeat of the above test after selection of final conditions (i.e., pH, temperature) if they differ from conditions tested.

Taylor-Pashow, K.

2012-08-09T23:59:59.000Z

26

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

27

Los Alamos National Laboratory summary plan to fabricate mixed oxide lead assemblies for the fissile material disposition program  

SciTech Connect (OSTI)

This report summarizes an approach for using existing Los Alamos National Laboratory (Laboratory) mixed oxide (MOX) fuel-fabrication and plutonium processing capabilities to expedite and assure progress in the MOX/Reactor Plutonium Disposition Program. Lead Assembly MOX fabrication is required to provide prototypic fuel for testing in support of fuel qualification and licensing requirements. It is also required to provide a bridge for the full utilization of the European fabrication experience. In part, this bridge helps establish, for the first time since the early 1980s, a US experience base for meeting the safety, licensing, safeguards, security, and materials control and accountability requirements of the Department of Energy and Nuclear Regulatory Commission. In addition, a link is needed between the current research and development program and the production of disposition mission fuel. This link would also help provide a knowledge base for US regulators. Early MOX fabrication and irradiation testing in commercial nuclear reactors would provide a positive demonstration to Russia (and to potential vendors, designers, fabricators, and utilities) that the US has serious intent to proceed with plutonium disposition. This report summarizes an approach to fabricating lead assembly MOX fuel using the existing MOX fuel-fabrication infrastructure at the Laboratory.

Buksa, J.J.; Eaton, S.L.; Trellue, H.R.; Chidester, K.; Bowidowicz, M.; Morley, R.A.; Barr, M.

1997-12-01T23:59:59.000Z

28

HEU to LEU Conversion and Blending Facility: UNH blending alternative to produce LEU UNH for commercial use  

SciTech Connect (OSTI)

US DOE is examining options for disposing of surplus weapons-usable fissile materials and storage of all weapons-usable fissile materials. The nuclear material is converted to a form that is more proliferation-resistant than the original form. Examining options for increasing the proliferation resistance of highly enriched uranium (HEU) is part of this effort. Five technologies for blending HEU will be assessed. This document provides data to be used in the environmental impact analysis for the UNH blending HEU disposition option. Process requirements, resource needs, employment needs, waste/emissions from plant, hazards, accident scenarios, and intersite transportation are discussed.

NONE

1995-09-01T23:59:59.000Z

29

APPLICATION OF NONSPHERICAL FISSILE CONFIGURATION IN WASTE CONTAINERS AT SRS  

SciTech Connect (OSTI)

Transuranic (TRU) solid waste that has been generated as a result of the production of nuclear material for the United States defense program at the Savannah River Site (SRS) has been stored in more than 30,000 55-gallon drums and carbon steel boxes since 1953. Nearly two thirds of those containers have been processed and shipped to the Waste Isolation Pilot Plant. Among the containers assayed so far, the results indicate several drums with fissile inventories significantly higher (600-1000 fissile grams equivalent (FGE) {sup 239}Pu) than their original assigned values. While part of this discrepancy can be attributed to the past limited assay capabilities, human errors are believed to be the primary contributor. This paper summarizes the application of nonspherical fissile material configuration in waste containers, resulting in less restrictive mass and spacing limits, increased storage capacity, and several administrative controls for handling and storage of waste containers being modified without compromising safety.

Eghbali, D; Michelle Abney, M

2007-01-03T23:59:59.000Z

30

Fissile solution dynamics: Student research  

SciTech Connect (OSTI)

There are two research projects in criticality safety at the University of Arizona: one in dynamic simulation of hypothetical criticality accidents in fissile solutions, and one in criticality benchmarks using transport theory. We have used the data from nuclear excursions in KEWB, CRAC, and SILENE to help in building models for solution excursions. An equation of state for liquids containing gas bubbles has been developed and coupled to point-reactor dynamics in an attempt to predict fission rate, yield, pressure, and kinetic energy. It appears that radiolytic gas is unimportant until after the first peak, but that it does strongly affect the shape of the subsequent power decrease and also the dynamic pressure.

Hetrick, D.L.

1994-09-01T23:59:59.000Z

31

fissile material | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

32

United States, International Partners Remove Last Remaining Weapons-Usable  

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) "ofEarlyEnergyDepartment of EnergyProgram2-26The Confederated Tribes7325.8Assessmentof AmericaHighly

33

US-Russian Cooperation in Upgrading MC&A System at Rosatom Facilities: Measurement of Nuclear Materials  

SciTech Connect (OSTI)

Improve protection of weapons-usable nuclear material from theft or diversion through the development and support of a nationwide sustainable and effective Material Control and Accountability (MC&A) program based on material measurement. The material protection, control, and accountability (MPC&A) cooperation has yielded significant results in implementing MC&A measurements at Russian nuclear facilities: (1) Establishment of MEM WG and MEMS SP; (2) Infrastructure for development, certification, and distribution of RMs; and (3) Coordination on development and implementation of MMs.

Powell, Danny H [ORNL] [ORNL; Jensen, Bruce A [ORNL] [ORNL

2011-01-01T23:59:59.000Z

34

FMDP reactor alternative summary report. Volume 1 - existing LWR alternative  

SciTech Connect (OSTI)

Significant quantities of weapons-usable fissile materials [primarily plutonium and highly enriched uranium (HEU)] are becoming surplus to national defense needs in both the United States and Russia. These stocks of fissile materials pose significant dangers to national and international security. The dangers exist not only in the potential proliferation of nuclear weapons but also in the potential for environmental, safety, and health (ES&H) consequences if surplus fissile materials are not properly managed. This document summarizes the results of analysis concerned with existing light water reactor plutonium disposition alternatives.

Greene, S.R.; Bevard, B.B. [and others

1996-10-07T23:59:59.000Z

35

HEU to LEU Conversion and Blending Facility: UF{sub 6} blending alternative to produce LEU UF{sub 6} for commercial use  

SciTech Connect (OSTI)

US DOE is examining options for disposing of surplus weapons-usable fissile materials and storage of all weapons-usable fissile materials; the nuclear material will be converted to a form more proliferation- resistant than the original form. Examining options for increasing the proliferation resistance of highly enriched uranium (HEU) is part of this effort. Five technologies for blending HEU will be assessed; blending as UF{sub 6} to produce a UF{sub 6} product for commercial use is one of them. This document provides data to be used in the environmental impact analysis for the UF{sub 6} blending HEU disposition option. Resource needs, employment needs, waste and emissions from plant, hazards, accident scenarios, and intersite transportation are discussed.

NONE

1995-09-01T23:59:59.000Z

36

HEU to LEU conversion and blending facility: Metal blending alternative to produce LEU oxide for disposal  

SciTech Connect (OSTI)

US DOE is examining options for disposing of surplus weapons-usable fissile materials and storage of all weapons-usable fissile materials. The nuclear material is converted to a form more proliferation- resistant than the original form. Blending HEU (highly enriched uranium) with less-enriched uranium to form LEU has been proposed as a disposition option. Five technologies are being assessed for blending HEU. This document provides data to be used in environmental impact analysis for the HEU-LEU disposition option that uses metal blending with an oxide waste product. It is divided into: mission and assumptions, conversion and blending facility descriptions, process descriptions and requirements, resource needs, employment needs, waste and emissions from plant, hazards discussion, and intersite transportation.

NONE

1995-09-01T23:59:59.000Z

37

LIFE Materials: Overview of Fuels and Structural Materials Issues Volume 1  

SciTech Connect (OSTI)

The National Ignition Facility (NIF) project, a laser-based Inertial Confinement Fusion (ICF) experiment designed to achieve thermonuclear fusion ignition and burn in the laboratory, is under construction at the Lawrence Livermore National Laboratory (LLNL) and will be completed in April of 2009. Experiments designed to accomplish the NIF's goal will commence in late FY2010 utilizing laser energies of 1 to 1.3 MJ. Fusion yields of the order of 10 to 20 MJ are expected soon thereafter. Laser initiated fusion-fission (LIFE) engines have now been designed to produce nuclear power from natural or depleted uranium without isotopic enrichment, and from spent nuclear fuel from light water reactors without chemical separation into weapons-attractive actinide streams. A point-source of high-energy neutrons produced by laser-generated, thermonuclear fusion within a target is used to achieve ultra-deep burn-up of the fertile or fissile fuel in a sub-critical fission blanket. Fertile fuels including depleted uranium (DU), natural uranium (NatU), spent nuclear fuel (SNF), and thorium (Th) can be used. Fissile fuels such as low-enrichment uranium (LEU), excess weapons plutonium (WG-Pu), and excess highly-enriched uranium (HEU) may be used as well. Based upon preliminary analyses, it is believed that LIFE could help meet worldwide electricity needs in a safe and sustainable manner, while drastically shrinking the nation's and world's stockpile of spent nuclear fuel and excess weapons materials. LIFE takes advantage of the significant advances in laser-based inertial confinement fusion that are taking place at the NIF at LLNL where it is expected that thermonuclear ignition will be achieved in the 2010-2011 timeframe. Starting from as little as 300 to 500 MW of fusion power, a single LIFE engine will be able to generate 2000 to 3000 MWt in steady state for periods of years to decades, depending on the nuclear fuel and engine configuration. Because the fission blanket in a fusion-fission hybrid system is subcritical, a LIFE engine can burn any fertile or fissile nuclear material, including un-enriched natural or depleted U and SNF, and can extract a very high percentage of the energy content of its fuel resulting in greatly enhanced energy generation per metric ton of nuclear fuel, as well as nuclear waste forms with vastly reduced concentrations of long-lived actinides. LIFE engines could thus provide the ability to generate vast amounts of electricity while greatly reducing the actinide content of any existing or future nuclear waste and extending the availability of low cost nuclear fuels for several thousand years. LIFE also provides an attractive pathway for burning excess weapons Pu to over 99% FIMA (fission of initial metal atoms) without the need for fabricating or reprocessing mixed oxide fuels (MOX). Because of all of these advantages, LIFE engines offer a pathway toward sustainable and safe nuclear power that significantly mitigates nuclear proliferation concerns and minimizes nuclear waste. An important aspect of a LIFE engine is the fact that there is no need to extract the fission fuel from the fission blanket before it is burned to the desired final level. Except for fuel inspection and maintenance process times, the nuclear fuel is always within the core of the reactor and no weapons-attractive materials are available outside at any point in time. However, an important consideration when discussing proliferation concerns associated with any nuclear fuel cycle is the ease with which reactor fuel can be converted to weapons usable materials, not just when it is extracted as waste, but at any point in the fuel cycle. Although the nuclear fuel remains in the core of the engine until ultra deep actinide burn up is achieved, soon after start up of the engine, once the system breeds up to full power, several tons of fissile material is present in the fission blanket. However, this fissile material is widely dispersed in millions of fuel pebbles, which can be tagged as individual accountable items, and thus made difficult to dive

Farmer, J

2008-09-08T23:59:59.000Z

38

Fissile sample worths in the Uranium/Iron Benchmark  

SciTech Connect (OSTI)

One of the long-standing problems from LMFBR critical experiments is the central worth discrepancy, the consistent overprediction of the reactivity associated with introducing a small material sample near the center of an assembly. Reactivity (sample worth) experiments in ZPR-9, assembly 34, the Uranium/Iron Benchmark (U/Fe), were aimed at investigating this discrepancy. U/Fe had a large, single-region core whose neutronics was governed almost entirely by /sup 235/U and iron. The essentially one-dimensional plate unit cell had one 1.6 mm-wide column of 93% enriched uranium (U(93)) near the center, imbedded in about 50 mm of iron and stainless steel. The neutron spectrum was roughly comparable to that of an LMFBR, but the adjoint spectrum was much flatter than an LMFBR's. The worths of four different fissile materials were measured and the worth of U(93) was measured using several different experimental techniques.

Schaefer, R.W.; Bucher, R.G.

1983-01-01T23:59:59.000Z

39

Fusion-Fission Hybrid for Fissile Fuel Production without Processing  

SciTech Connect (OSTI)

Two scenarios are typically envisioned for thorium fuel cycles: 'open' cycles based on irradiation of {sup 232}Th and fission of {sup 233}U in situ without reprocessing or 'closed' cycles based on irradiation of {sup 232}Th followed by reprocessing, and recycling of {sup 233}U either in situ or in critical fission reactors. This study evaluates a third option based on the possibility of breeding fissile material in a fusion-fission hybrid reactor and burning the same fuel in a critical reactor without any reprocessing or reconditioning. This fuel cycle requires the hybrid and the critical reactor to use the same fuel form. TRISO particles embedded in carbon pebbles were selected as the preferred form of fuel and an inertial laser fusion system featuring a subcritical blanket was combined with critical pebble bed reactors, either gas-cooled or liquid-salt-cooled. The hybrid reactor was modeled based on the earlier, hybrid version of the LLNL Laser Inertial Fusion Energy (LIFE1) system, whereas the critical reactors were modeled according to the Pebble Bed Modular Reactor (PBMR) and the Pebble Bed Advanced High Temperature Reactor (PB-AHTR) design. An extensive neutronic analysis was carried out for both the hybrid and the fission reactors in order to track the fuel composition at each stage of the fuel cycle and ultimately determine the plant support ratio, which has been defined as the ratio between the thermal power generated in fission reactors and the fusion power required to breed the fissile fuel burnt in these fission reactors. It was found that the maximum attainable plant support ratio for a thorium fuel cycle that employs neither enrichment nor reprocessing is about 2. This requires tuning the neutron energy towards high energy for breeding and towards thermal energy for burning. A high fuel loading in the pebbles allows a faster spectrum in the hybrid blanket; mixing dummy carbon pebbles with fuel pebbles enables a softer spectrum in the critical reactors. This combination consumes about 20% of the thorium initially loaded in the hybrid reactor ({approx}200 GWd/tHM), partially during hybrid operation, but mostly during operation in the critical reactor. The plant support ratio is low compared to the one attainable using continuous fuel chemical reprocessing, which can yield a plant support ratio of about 20, but the resulting fuel cycle offers better proliferation resistance as fissile material is never separated from the other fuel components.

Fratoni, M; Moir, R W; Kramer, K J; Latkowski, J F; Meier, W R; Powers, J J

2012-01-02T23:59:59.000Z

40

Proliferation Risks of Fusion Energy: Clandestine Production, Covert Production, and Breakout  

SciTech Connect (OSTI)

Nuclear proliferation risks from fusion associated with access to weapon-usable material can be divided into three main categories: 1) clandestine production of fissile material in an undeclared facility, 2) covert production of such material in a declared and safeguarded facility, and 3) use of a declared facility in a breakout scenario, in which a state begins production of fissile material without concealing the effort. In this paper we address each of these categories of risk from fusion. For each case, we find that the proliferation risk from fusion systems can be much lower than the equivalent risk from fission systems, if commercial fusion systems are designed to accommodate appropriate safeguards.

R.J. Goldston, A. Glaser, A.F. Ross

2009-08-13T23:59:59.000Z

Note: This page contains sample records for the topic "weapons-usable fissile materials" 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

TYPE A FISSILE PACKAGING FOR AIR TRANSPORT PROJECT OVERVIEW  

SciTech Connect (OSTI)

This paper presents the project status of the Model 9980, a new Type A fissile packaging for use in air transport. The Savannah River National Laboratory (SRNL) developed this new packaging to be a light weight (<150-lb), drum-style package and prepared a Safety Analysis for Packaging (SARP) for submission to the DOE/EM. The package design incorporates unique features and engineered materials specifically designed to minimize packaging weight and to be in compliance with 10CFR71 requirements. Prototypes were fabricated and tested to evaluate the design when subjected to Normal Conditions of Transport (NCT) and Hypothetical Accident Conditions (HAC). An overview of the design details, results of the regulatory testing, and lessons learned from the prototype fabrication for the 9980 will be presented.

Eberl, K.; Blanton, P.

2013-10-11T23:59:59.000Z

42

Surplus Plutonium Disposition Final Environmental Impact Statement  

SciTech Connect (OSTI)

In December 1996, the U.S. Department of Energy (DOE) published the ''Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic Environmental Impact Statement (Storage and Disposition PEIS)'' (DOE 1996a). That PEIS analyzes the potential environmental consequences of alternative strategies for the long-term storage of weapons-usable plutonium and highly enriched uranium (HEU) and the disposition of weapons-usable plutonium that has been or may be declared surplus to national security needs. The Record of Decision (ROD) for the ''Storage and Disposition PEIS'', issued on January 14, 1997 (DOE 1997a), outlines DOE's decision to pursue an approach to plutonium disposition that would make surplus weapons-usable plutonium inaccessible and unattractive for weapons use. DOE's disposition strategy, consistent with the Preferred Alternative analyzed in the ''Storage and Disposition PEIS'', allows for both the immobilization of some (and potentially all) of the surplus plutonium and use of some of the surplus plutonium as mixed oxide (MOX) fuel in existing domestic, commercial reactors. The disposition of surplus plutonium would also involve disposal of both the immobilized plutonium and the MOX fuel (as spent nuclear fuel) in a potential geologic repository.

N /A

1999-11-19T23:59:59.000Z

43

E-Print Network 3.0 - aqueous fissile solutions Sample Search...  

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

fissile solutions Search Powered by Explorit Topic List Advanced Search Sample search results for: aqueous fissile solutions Page: << < 1 2 3 4 5 > >> 1 Molten salts and nuclear...

44

Criticality safety of an annular tank for fissile solution  

SciTech Connect (OSTI)

Experiments performed to determine the criticality safety of annular tanks for storing fissile solutions are described. Six annular tanks were built in four nesting sizes to obtain experimental criticality data which could be used to validate computer codes employed in the design of such a safe storage system for an industrial plant. Each tank had an annular solution region thickness of 38 mm. The height of this region was 2.13 m, held 0.3 m off the floor by a stainless steel skirting. Walls were 6.4 mm-thick type 304L stainless steel. The uranyl nitrate solution contained 357 g U/l and had a density of 1.5 kg/m/sup 3/. The uranium was enriched to 93.2% /sup 235/U with other isotopes: 5.4% /sup 238/U, 1.0% /sup 234/U, and 0.4% /sup 236/U. The solution contained 0.5 molar nitric acid and a total impurity content of less than 1500 ppM. Important neutron absorbers, boron and cadmium, averaged 10 ppM and 30 ppM, respectively. Boron-loaded concrete and boron-loaded plaster were selected for the neutron moderator/absorber interior to the annular tank. Three configurations of tanks and reflector were taken to criticality and are reported. The critical uranium solution height in all tanks containing solution as a function of boron content in earthen interior material, tank array configuration, and other variables. (LCL)

Rothe, R.E.

1981-01-01T23:59:59.000Z

45

Fissile interrogation using gamma rays from oxygen  

DOE Patents [OSTI]

The subject apparatus provides a means to identify the presence of fissionable material or other nuclear material contained within an item to be tested. The system employs a portable accelerator to accelerate and direct protons to a fluorine-compound target. The interaction of the protons with the fluorine-compound target produces gamma rays which are directed at the item to be tested. If the item to be tested contains either a fissionable material or other nuclear material the interaction of the gamma rays with the material contained within the test item with result in the production of neutrons. A system of neutron detectors is positioned to intercept any neutrons generated by the test item. The results from the neutron detectors are analyzed to determine the presence of a fissionable material or other nuclear material.

Smith, Donald; Micklich, Bradley J.; Fessler, Andreas

2004-04-20T23:59:59.000Z

46

Characterization of fissile material using low energy neutron interrogation  

E-Print Network [OSTI]

The glaring need to develop methods for detecting and interdicting illicit nuclear trafficking has resulted in the exploration of various methods for active neutron interrogation, specifically for the presence of special ...

Padilla, Eduardo A

2007-01-01T23:59:59.000Z

47

Remote detection of fissile material : Cherenkov counters for gamma detection  

E-Print Network [OSTI]

The need for large-size detectors for long-range active interrogation (Al) detection has generated interest in water-based detector technologies. AI is done using external radiation sources to induce fission and to detect, ...

Erickson, Anna S

2011-01-01T23:59:59.000Z

48

Impact of delayed neutron precursor mobility in fissile solution systems  

SciTech Connect (OSTI)

A research version of the Monte Carlo software package MCNP6 is modified to incorporate advection and diffusion of delayed neutron precursors, resulting in the emission of delayed neutrons at locations different from the original fission sites. Results of two test problems, a pipe carrying flowing fissile solution and a sphere of fissile solution with precursor diffusion, show that the fission product mobility tends to perturb the fundamental mode, has a negative reactivity effect, and, perhaps most importantly, causes a decrease in the effective delayed neutron fraction. (authors)

Kiedrowski, B. C. [X-Computational Physics Div., Los Alamos National Laboratory, MS A143, P.O. Box 1663, Los Alamos, NM 87545 (United States)

2012-07-01T23:59:59.000Z

49

R&D proliferation detection  

National Nuclear Security Administration (NNSA)

Security program collaborates with partners world-wide to improve the security of proliferation-sensitive materials, particularly weapons-usable nuclear material in both civilian...

50

Feasibility of fissile mass assay of spent nuclear fuel using {sup 252}Cf-source-driven frequency-analysis  

SciTech Connect (OSTI)

The feasibility was evaluated using MCNP-DSP, an analog Monte Carlo transport cod to simulate source-driven measurements. Models of an isolated Westinghouse 17x17 PWR fuel assembly in a 1500-ppM borated water storage pool were used. In the models, the fuel burnup profile was represented using seven axial burnup zones, each with isotopics estimated by the PDQ code. Four different fuel assemblies with average burnups from fresh to 32 GWd/MTU were modeled and analyzed. Analysis of the fuel assemblies was simulated by inducing fission in the fuel using a {sup 252}Cf source adjacent to the assembly and correlating source fissions with the response of a bank of {sup 3}He detectors adjacent to the assembly opposite the source. This analysis was performed at 7 different axial positions on each of the 4 assemblies, and the source-detector cross-spectrum signature was calculated for each of these 28 simulated measurements. The magnitude of the cross-spectrum signature follows a smooth upward trend with increasing fissile material ({sup 235}U and {sup 239}Pu) content, and the signature is independent of the concentration of spontaneously fissioning isotopes (e.g., {sup 244}Cm) and ({alpha},n) sources. Furthermore, the cross-spectrum signature is highly sensitive to changes in fissile material content. This feasibility study indicated that the signature would increase {similar_to}100% in response to an increase of only 0.1 g/cm{sup 3} of fissile material.

Mattingly, J.K.; Valentine, T.E.; Mihalczo, J.T.

1996-10-01T23:59:59.000Z

51

The Role of the George Kuzmycz Training Center in Improving the Nuclear Material Management Culture in Ukraine.  

SciTech Connect (OSTI)

The George Kuzmycz Training Center for Physical Protection, Control and Accounting (GKTC) was established in 1998 in a collaborative endeavor of the State Nuclear Regulatory Administration of Ukraine, the Ukrainian Academy of Sciences, and the U.S. Department of Energy. Located at the Institute for Nuclear Research in Kyiv, the GKTC provides theoretical and practical training in physical protection, control, and accounting techniques and systems that are employed to reduce the risk of unauthorized use, theft, or diversion of weapons-usable nuclear material. Participants in GKTC workshops and courses include nuclear facility specialists as well as officials of the State's regulatory authorities. Recently, the training scope has been broadened to include students from other nations in the region.

Gavrylyuk, V. I. (Viktor I.); Scherbachenko, A. M. (Alexander M.); Bazavov, D. A. (Dmitri A.); Kyryshchuk, V. I. (Volodymyr I.); Robinson, P. (Phil); Sheppard, G. A. (Gregory A.)

2001-01-01T23:59:59.000Z

52

U.S. weapons-usable plutonium disposition policy: Implementation of the MOX fuel option  

SciTech Connect (OSTI)

A comprehensive case study was conducted on the policy problem of disposing of US weapons-grade plutonium, which has been declared surplus to strategic defense needs. Specifically, implementation of the mixed-oxide fuel disposition option was examined in the context of national and international nonproliferation policy, and in contrast to US plutonium policy. The study reveals numerous difficulties in achieving effective implementation of the mixed-oxide fuel option including unresolved licensing and regulatory issues, technological uncertainties, public opposition, potentially conflicting federal policies, and the need for international assurances of reciprocal plutonium disposition activities. It is believed that these difficulties can be resolved in time so that the implementation of the mixed-oxide fuel option can eventually be effective in accomplishing its policy objective.

Woods, A.L. [ed.] [Amarillo National Resource Center for Plutonium, TX (United States); Gonzalez, V.L. [Texas A and M Univ., College Station, TX (United States). Dept. of Political Science

1998-10-01T23:59:59.000Z

53

DEVELOPMENT OF THE HS99 AIR TRANSPORT TYPE A FISSILE PACKAGE  

SciTech Connect (OSTI)

An air-transport Type A Fissile radioactive shipping package for the transport of special form uranium sources has been developed by the Savannah River National Laboratory (SRNL) for the Department of Homeland Security. The Package model number is HS99 for Homeland Security Model 99. This paper presents the major design features of the HS99 and highlights engineered materials necessary for meeting the design requirements for this light-weight Type AF packaging. A discussion is provided demonstrating how the HS99 complies with the regulatory safety requirements of the Nuclear Regulatory Commission. The paper summarizes the results of structural testing to specified in 10 CFR 71 for Normal Conditions of Transport and Hypothetical Accident Conditions events. Planned and proposed future missions for this packaging are also addressed.

Blanton, P.; Eberl, K.

2012-07-10T23:59:59.000Z

54

HEU to LEU conversion and blending facility: UNH blending alternative to produce LEU oxide for disposal  

SciTech Connect (OSTI)

The United States Department of Energy (DOE) is examining options for the disposition of surplus weapons-usable fissile materials and storage of all weapons-usable fissile materials. Disposition is a process of use or disposal of material that results in the material being converted to a form that is substantially and inherently more proliferation-resistant than is the original form. Examining options for increasing the proliferation resistance of highly enriched uranium (HEU) is part of this effort. This report provides data to be used in the environmental impact analysis for the uranyl nitrate hexahydrate blending option to produce oxide for disposal. This the Conversion and Blending Facility (CBF) alternative will have two missions (1) convert HEU materials into HEU uranyl nitrate (UNH) and (2) blend the HEU uranyl nitrate with depleted and natural assay uranyl nitrate to produce an oxide that can be stored until an acceptable disposal approach is available. The primary emphasis of this blending operation will be to destroy the weapons capability of large, surplus stockpiles of HEU. The blended LEU product can only be made weapons capable again by the uranium enrichment process. The blended LEU will be produced as a waste suitable for storage or disposal.

NONE

1995-09-01T23:59:59.000Z

55

Apparatus and method for quantitatively evaluating total fissile and total fertile nuclide content in samples. [Patent application  

DOE Patents [OSTI]

Simultaneous photon and neutron interrogation of samples for the quantitative determination of total fissile nuclide and total fertile nuclide material present is made possible by the use of an electron accelerator. Prompt and delayed neutrons produced from resulting induced fission are counted using a single detection system and allow the resolution of the contributions from each interrogating flux leading in turn to the quantitative determination sought. Detection limits for /sup 239/Pu are estimated to be about 3 mg using prompt fission neutrons and about 6 mg using delayed neutrons.

Caldwell, J.T.; Kunz, W.E.; Cates, M.R.; Franks, L.A.

1982-07-07T23:59:59.000Z

56

HEU to LEU conversion and blending facility: Oxide blending alternative to produce LEU oxide for commercial use  

SciTech Connect (OSTI)

The United States Department of Energy (DOE) is examining options for the disposition of surplus weapons-usable fissile materials and storage of all weapons-usable fissile materials. Disposition is a process of use or disposal of material that results in the material being converted to a form that is substantially and inherently more proliferation-resistant than the original form. Examining options for increasing the proliferation resistance of highly enriched uranium (HEU) is part of this effort. This document provides data to be used in the environmental impact analysis for the oxide blending HEU disposition option. This option provides for a yearly HEU throughput of 1 0 metric tons (MT) of uranium metal with an average U235 assay of 50% blended with 165 MT of natural assay triuranium octoxide (U{sub 3} O{sub 8}) per year to produce 177 MT of 4% U235 assay U{sub 3} O{sub 8}, for LWR fuel. Since HEU exists in a variety of forms and not necessarily in the form to be blended, worst case scenarios for preprocessing prior to blending will be assumed for HEU feed streams.

NONE

1995-09-01T23:59:59.000Z

57

MOX Lead Assembly Fabrication at the Savannah River Site  

SciTech Connect (OSTI)

The U. S. Department of Energy (DOE) announced its intent to prepare an Environmental Impact Statement (EIS) under the National Environmental Policy Act (NEPA) on the disposition of the nations weapon-usable surplus plutonium.This EIS is tiered from the Storage and Disposition of Weapons-Usable Fissile Material Programmatic Environmental Impact Statement issued in December 1996,and the associated Record of Decision issued on January, 1997. The EIS will examine reasonable alternatives and potential environmental impacts for the proposed siting, construction, and operation of three types of facilities for plutonium disposition. The three types of facilities are: a pit disassembly and conversion facility, a facility to immobilize surplus plutonium in a glass or ceramic form for disposition, and a facility to fabricate plutonium oxide into mixed oxide (MOX) fuel.As an integral part of the surplus plutonium program, Oak Ridge National Laboratory (ORNL) was tasked by the DOE Office of Fissile Material Disposition(MD) as the technical lead to organize and evaluate existing facilities in the DOE complex which may meet MD`s need for a domestic MOX fuel fabrication demonstration facility. The Lead Assembly (LA) facility is to produce 1 MT of usable test fuel per year for three years. The Savannah River Site (SRS) as the only operating plutonium processing site in the DOE complex, proposes two options to carry out the fabrication of MOX fuel lead test assemblies: an all Category I facility option and a combined Category I and non-Category I facilities option.

Geddes, R.L. [Westinghouse Savannah River Company, AIKEN, SC (United States); Spiker, D.L.; Poon, A.P.

1997-12-01T23:59:59.000Z

58

Global threat reduction initiative Russian nuclear material removal progress  

SciTech Connect (OSTI)

In December 1999 representatives from the United States, the Russian Federation, and the International Atomic Energy Agency (IAEA) started discussing a program to return to Russia Soviet- or Russian-supplied highly enriched uranium (HEU) fuel stored at the Russian-designed research reactors outside Russia. Trilateral discussions among the United States, Russian Federation, and the International Atomic Energy Agency (IAEA) have identified more than 20 research reactors in 17 countries that have Soviet- or Russian-supplied HEU fuel. The Global Threat Reduction Initiative's Russian Research Reactor Fuel Return Program is an important aspect of the U.S. Government's commitment to cooperate with the other nations to prevent the proliferation of nuclear weapons and weapons-usable proliferation-attractive nuclear materials. To date, 496 kilograms of Russian-origin HEU have been shipped to Russia from Serbia, Latvia, Libya, Uzbekistan, Romania, Bulgaria, Poland, Germany, and the Czech Republic. The pilot spent fuel shipment from Uzbekistan to Russia was completed in April 2006. (author)

Cummins, Kelly [DOE/NNSA (United States); Bolshinsky, Igor [INL/NNSA (United States)

2008-07-15T23:59:59.000Z

59

Integrated development and testing plan for the plutonium immobilization project  

SciTech Connect (OSTI)

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

Kan, T.

1998-07-01T23:59:59.000Z

60

Comparison of thorium-based fuels with different fissile components in existing boiling water reactors  

E-Print Network [OSTI]

Comparison of thorium-based fuels with different fissile components in existing boiling water, SE-412 96 Göteborg, Sweden Keywords: Thorium BWR Neutronics a b s t r a c t With the aim of investigating the technical feasibility of fuelling a conventional BWR (Boiling Water Reactor) with thorium

Demazière, Christophe

Note: This page contains sample records for the topic "weapons-usable fissile materials" 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

Evaluation Of Glass Density To Support The Estimation Of Fissile Mass Loadings From Iron Concentrations In SB8 Glasses  

SciTech Connect (OSTI)

The Department of Energy Savannah River (DOE-SR) has provided direction to Savannah River Remediation (SRR) to maintain fissile concentration in glass below 897 g/m{sup 3}. In support of that guidance, the Savannah River National Laboratory (SRNL) provided a technical basis and a supporting Microsoft Excel spreadsheet for the evaluation of fissile loading in Sludge Batch 5 (SB5), Sludge Batch 6 (SB6), Sludge Batch 7a (SB7a), and Sludge Batch 7b (SB7b) glass based on the iron (Fe) concentration in glass as determined by the measurements from the Slurry Mix Evaporator (SME) acceptability analysis. SRR has since requested that the necessary density information be provided to allow SRR to update the Excel spreadsheet so that it may be used to maintain fissile concentration in glass below 897 g/m{sup 3} during the processing of Sludge Batch 8 (SB8). One of the primary inputs into the fissile loading spreadsheet includes an upper bound for the density of SB8-based glasses. Thus, these bounding density values are to be used to assess the fissile concentration in this glass system. It should be noted that no changes are needed to the underlying structure of the Excel-based spreadsheet to support fissile assessments for SB8. However, SRR should update the other key inputs to the spreadsheet that are based on fissile and Fe concentrations reported from the SB8 Waste Acceptance Product Specification (WAPS) sample.

Edwards, T. B.; Peeler, D. K.; Kot, W. K.; Gan, H.; Pegg, I. L.

2013-04-30T23:59:59.000Z

62

FMDP reactor alternative summary report: Volume 4, Evolutionary LWR alternative  

SciTech Connect (OSTI)

Significant quantities of weapons-usable fissile materials [primarily plutonium and highly enriched uranium (HEU)] have become surplus to national defense needs both in the United States and Russia. These stocks of fissile materials pose significant dangers to national and international security. The dangers exist not only in the potential proliferation of nuclear weapons but also in the potential for environmental, safety, and health (ES&H) consequences if surplus fissile materials are not properly managed. The purpose of this report is to provide schedule, cost, and technical information that will be used to support the Record of Process (ROD). Following the screening process, DOE/MD via its national laboratories initiated a more detailed analysis activity to further evaluate each of the ten plutonium disposition alternatives that survived the screening process. Three ``Alternative Teams,`` chartered by DOE and comprised of technical experts from across the DOE national laboratory complex, conducted these analyses. One team was chartered for each of the major disposition classes (borehole, immobilization, and reactors). During the last year and a half, the Fissile Materials Disposition Program (FMDP) Reactor Alternative Team (RxAT) has conducted extensive analyses of the cost, schedule, technical maturity, S&S, and other characteristics of reactor-based plutonium disposition. The results of the RxAT`s analyses of the existing LWR, CANDU, and partially complete LWR alternatives are documented in Volumes 1-3 of this report. This document (Volume 4) summarizes the results of these analyses for the ELWR-based plutonium disposition option.

NONE

1996-09-01T23:59:59.000Z

63

International Nuclear Security  

SciTech Connect (OSTI)

This presentation discusses: (1) Definitions of international nuclear security; (2) What degree of security do we have now; (3) Limitations of a nuclear security strategy focused on national lock-downs of fissile materials and weapons; (4) What do current trends say about the future; and (5) How can nuclear security be strengthened? Nuclear security can be strengthened by: (1) More accurate baseline inventories; (2) Better physical protection, control and accounting; (3) Effective personnel reliability programs; (4) Minimize weapons-usable materials and consolidate to fewer locations; (5) Consider local threat environment when siting facilities; (6) Implement pledges made in the NSS process; and (7) More robust interdiction, emergency response and special operations capabilities. International cooperation is desirable, but not always possible.

Doyle, James E. [Los Alamos National Laboratory

2012-08-14T23:59:59.000Z

64

Measuring of fissile isotopes partial antineutrino spectra in direct experiment at nuclear reactor  

E-Print Network [OSTI]

The direct measuring method is considered to get nuclear reactor antineutrino spectrum. We suppose to isolate partial spectra of the fissile isotopes by using the method of antineutrino spectrum extraction from the inverse beta decay positron spectrum applied at Rovno experiment. This admits to increase the accuracy of partial antineutrino spectra forming the total nuclear reactor spectrum. It is important for the analysis of the reactor core fuel composition and could be applied for non-proliferation purposes.

V. V. Sinev

2009-02-22T23:59:59.000Z

65

Feasibility analysis of scanning 100% of maritime cargo containers for fissile material  

E-Print Network [OSTI]

On August 3, 2007, President George W. Bush signed into law H.R. 1: Implementing Recommendations of the 9/11 Commission Act of 2007. The law mandates that 100% of air and maritime cargo must be scanned prior to entering ...

Foley, William E., III

2008-01-01T23:59:59.000Z

66

Measurements on an inventory of mixed fissile materials in shipping containers  

SciTech Connect (OSTI)

An inventory contained a large number of previously unmeasured items, many with both uranium and plutonium. We have assembled a suite of instruments and measured the items in a variety of ways. This report first considers the measurements and deduced results in detail before summarizing the important differences with the declarations of the inventory`s database. The appendices referred to in this report are part of a classified version only and are not attached to this unclassified version. The classified report is by the same authors as this report, has the same title (which is unclassified), and is classified as {open_quotes}SRD.{close_quotes}

Rinard, P.M.; Krick, M.S.; Kelley, T.A. [and others

1997-09-01T23:59:59.000Z

67

Nondestructive assay (NDA) of fissile material in gloveboxes and equipment at Rocky Flats Environmental Technology Site  

SciTech Connect (OSTI)

At Rocky Flats Environmental Technology Site (RFETS), a glovebox and equipment holdup measurement program called Untoward Areas was performed in FY92. These measurements were completed in selected areas of one building. After completing this task, measurements in two other buildings had been completed to assist in characterizing their entire inventory. This information was used as part of evaluating safeguards and security requirements. However, a large percent of the gloveboxes and equipment in process buildings have not been measured. Before FY97, holdup measurements were being performed prior to decommissioning and deactivation activities. To accelerate the quantification of holdup a list of areas suspected to have high amounts of holdup was compiled and funding was requested and recently received. Glovebox and equipment locations were selected by use of several selection criteria. The following steps were taken in the selection process: (1) attribute scan results (FY95) were examined and high scan result locations were selected, (2) knowledgeable personnel within and outside the organization were consulted, and (3) video characterization of the Building 707 chainveyor system was examined. Only a few of the high scan result areas from the attribute scan list had not been identified by the use of process knowledge. The primary driver for holdup measurements is Department of energy (DOE) Order 5633.3B, Section II-3, Physical Inventories.

Dreher, D.J.; Lamb, F.W.

1997-10-01T23:59:59.000Z

68

Commissioning Measurements and Experience Obtained from the Installation of a Fissile Mass Flow monitor in the URAL Electrochemical Integrated Plant (UEIP) in Novouralsk  

SciTech Connect (OSTI)

The Blend Down Monitoring System (BDMS) equipment sent earlier to the Ural Electrochemical Integrated Plant (UEIP) at Novouralsk, Russia, was installed and implemented successfully on February 2, 1999. The BDMS installation supports the highly enriched uranium (HEU) Transparency Implementation Program for material subject to monitoring under the HEU purchase agreement between the United States of America (USA) and the Russian Federation (RF). The BDMS consists of the Oak Ridge National Laboratory (ORNL) Fissile (uranium-235) Mass Flow Monitor (FMFM) and the Los Alamos National Laboratory (LANL) Enrichment Monitor (EM). Two BDMS?s for monitoring the Main and Reserve HEU blending process lines were installed at UEIP. Independent operation of the FMFM Main and FMFM Reserve was successfully demonstrated for monitoring the fissile mass flow as well as the traceability of HEU to the product low enriched uranium. The FMFM systems failed when both systems were activated during the calibration phase due to a synchronization problem between the systems. This operational failure was caused by the presence of strong electromagnetic interference (EMI) in the blend point. The source-modulator shutter motion of the two FMFM systems was not being properly synchronized because of EMI producing a spurious signal on the synchronization cable connecting the two FMFM cabinets. The signature of this failure was successfully reproduced at ORNL after the visit. This unexpected problem was eliminated by a hardware modification and software improvements during a recent visit (June 9-11, 1999) to UEIP, and both systems are now operating as expected.

March-Leuba, J.; Mastal, E.; Powell, D.; Sumner, J.; Uckan, T.; Vines, V.

1999-07-25T23:59:59.000Z

69

Ultraslow Wave Nuclear Burning of Uranium-Plutonium Fissile Medium on Epithermal Neutrons  

E-Print Network [OSTI]

For a fissile medium, originally consisting of uranium-238, the investigation of fulfillment of the wave burning criterion in a wide range of neutron energies is conducted for the first time, and a possibility of wave nuclear burning not only in the region of fast neutrons, but also for cold, epithermal and resonance ones is discovered for the first time. For the first time the results of the investigation of the Feoktistov criterion fulfillment for a fissile medium, originally consisting of uranium-238 dioxide with enrichments 4.38%, 2.00%, 1.00%, 0.71% and 0.50% with respect to uranium-235, in the region of neutron energies 0.015-10.0eV are presented. These results indicate a possibility of ultraslow wave neutron-nuclear burning mode realization in the uranium-plutonium media, originally (before the wave initiation by external neutron source) having enrichments with respect to uranium-235, corresponding to the subcritical state, in the regions of cold, thermal, epithermal and resonance neutrons. In order to validate the conclusions, based on the slow wave neutron-nuclear burning criterion fulfillment depending on the neutron energy, the numerical modeling of ultraslow wave neutron-nuclear burning of a natural uranium in the epithermal region of neutron energies (0.1-7.0eV) was conducted for the first time. The presented simulated results indicate the realization of the ultraslow wave neutron-nuclear burning of the natural uranium for the epithermal neutrons.

V. D. Rusov; V. A. Tarasov; M. V. Eingorn; S. A. Chernezhenko; A. A. Kakaev; V. M. Vashchenko; M. E. Beglaryan

2014-09-29T23:59:59.000Z

70

Influence of the Density Law on Various Fissile Single Unit and Array Storage Methods  

SciTech Connect (OSTI)

The advancement of computational technology has resulted in the wide-spread availability of powerful radiation transport Monte Carlo codes. Prevailing practices today rely heavily on Monte Carlo codes to provide the basis for assessing the reactivity of various fissile systems for nuclear criticality safety (NCS). In 1958, Weinberg and Wigner expressed their concerns on a 'deplorable trend in reactor design - the tendency to substitute a code for a theory'. Unfortunately, their concerns have largely become a reality in many modern NCS practices. lacking the time or information to understand the underlying neutron physics of the fissile system under consideration is indeed a deplorable trend. The purpose of this paper is to demonstrate that many features of criticality hand calculation methods are indeed based upon the fundamentals of the density law and that many correlations of important physics parameters can be more easily understood from such a perspective. Historically, the density law was recognized by many pioneers in the field, including during the Manhattan Project. However, it was by and large an 'oral tradition' in that bits and pieces of great physical insights of the pioneers were scattered in many earlier publications. This paper attempts to bring together some of the 'jewels' of the pioneers which might have been lost or forgotten.

Huang, S T

2011-03-02T23:59:59.000Z

71

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,...

72

Direct fissile assay of enriched uranium using random self-interrogation and neutron coincidence response  

DOE Patents [OSTI]

Apparatus and method for the direct, nondestructive evaluation of the .sup.235 U nuclide content of samples containing UF.sub.6, UF.sub.4, or UO.sub.2 utilizing the passive neutron self-interrogation of the sample resulting from the intrinsic production of neutrons therein. The ratio of the emitted neutron coincidence count rate to the total emitted neutron count rate is determined and yields a measure of the bulk fissile mass. The accuracy of the method is 6.8% (1.sigma.) for cylinders containing UF.sub.6 with enrichments ranging from 6% to 98% with measurement times varying from 3-6 min. The samples contained from below 1 kg to greater than 16 kg. Since the subject invention relies on fast neutron self-interrogation, complete sampling of the UF.sub.6 takes place, reducing difficulties arising from inhomogeneity of the sample which adversely affects other assay procedures.

Menlove, Howard O. (Los Alamos, NM); Stewart, James E. (Los Alamos, NM)

1986-01-01T23:59:59.000Z

73

Direct fissile assay of enriched uranium using random self-interrogation and neutron coincidence response  

DOE Patents [OSTI]

Apparatus and method for the direct, nondestructive evaluation of the /sup 235/U nuclide content of samples containing UF/sub 6/, UF/sub 4/, or UO/sub 2/ utilizing the passive neutron self-interrogation of the sample resulting from the intrinsic production of neutrons therein. The ratio of the emitted neutron coincidence count rate to the total emitted neutron count rate is determined and yields a measure of the bulk fissile mass. The accuracy of the method is 6.8% (1sigma) for cylinders containing UF/sub 6/ with enrichments ranging from 6% to 98% with measurement times varying from 3-6 min. The samples contained from below 1 kg to greater than 16 kg. Since the subject invention relies on fast neutron self-interrogation, complete sampling of the UF/sub 6/ takes place, reducing difficulties arising from inhomogeneity of the sample which adversely affects other assay procedures. 4 figs., 1 tab.

Menlove, H.O.; Stewart, J.E.

1985-02-04T23:59:59.000Z

74

Reducing nuclear danger through intergovernmental technical exchanges on nuclear materials safety management  

SciTech Connect (OSTI)

The United States and Russia are dismantling nuclear weapons and generating hundreds of tons of excess plutonium and high enriched uranium fissile nuclear materials that require disposition. The U.S. Department of Energy and Russian Minatom organizations.are planning and implementing safe, secure storage and disposition operations for these materials in numerous facilities. This provides a new opportunity for technical exchanges between Russian and Western scientists that can establish an improved and sustained common safety culture for handling these materials. An initiative that develops and uses personal relationships and joint projects among Russian and Western participants involved in fissile nuclear materials safety management contributes to improving nuclear materials nonproliferation and to making a safer world. Technical exchanges and workshops are being used to systematically identify opportunities in the nuclear fissile materials facilities to improve and ensure the safety of workers, the public, and the environment.

Jardine, L.J. [Lawrence Livermore National Lab., CA (United States); Peddicord, K.L. [Texas A and M Univ., College Station, TX (United States); Witmer, F.E.; Krumpe, P.F. [USDOE, Washington, DC (United States); Lazarev, L.; Moshkov, M. [Radievyj Inst., Leningrad (Russian Federation)

1997-04-09T23:59:59.000Z

75

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

76

Detecting fission from special nuclear material sources  

DOE Patents [OSTI]

A neutron detector system for discriminating fissile material from non-fissile material wherein a digital data acquisition unit collects data at high rate, and in real-time processes large volumes of data directly into information that a first responder can use to discriminate materials. The system comprises counting neutrons from the unknown source and detecting excess grouped neutrons to identify fission in the unknown source. The system includes a graphing component that displays the plot of the neutron distribution from the unknown source over a Poisson distribution and a plot of neutrons due to background or environmental sources. The system further includes a known neutron source placed in proximity to the unknown source to actively interrogate the unknown source in order to accentuate differences in neutron emission from the unknown source from Poisson distributions and/or environmental sources.

Rowland, Mark S. (Alamo, CA); Snyderman, Neal J. (Berkeley, CA)

2012-06-05T23:59:59.000Z

77

Nuclear materials safeguards for the future  

SciTech Connect (OSTI)

Basic concepts of domestic and international safeguards are described, with an emphasis on safeguards systems for the fuel cycles of commercial power reactors. Future trends in institutional and technical measures for nuclear materials safeguards are outlined. The conclusion is that continued developments in safeguards approaches and technology, coupled with institutional measures that facilitate the global management and protection of nuclear materials, are up to the challenge of safeguarding the growing inventories of nuclear materials in commercial fuel cycles in technologically advanced States with stable governments that have signed the nonproliferation treaty. These same approaches also show promise for facilitating international inspection of excess weapons materials and verifying a fissile materials cutoff convention.

Tape, J.W.

1995-12-31T23:59:59.000Z

78

Systems-based analysis of a ship borne approach for the detection of fissile material concealed in cargo containers  

E-Print Network [OSTI]

The international maritime container trade, which imports an average of 19,000 largely uninspected cargo containers to United States ports each day, has been identified as a potential avenue of attack for nuclear terrorism. ...

Broderick, Brett P

2004-01-01T23:59:59.000Z

79

Repackaging of High Fissile TRU Waste at the Transuranic Waste Processing Center - 13240  

SciTech Connect (OSTI)

Twenty-six drums of high fissile transuranic (TRU) waste from Oak Ridge National Laboratory (ORNL) operations were declared waste in the mid-1980's and placed in storage with the legacy TRU waste inventory for future treatment and disposal at the Waste Isolation Pilot Plant (WIPP). Repackaging and treatment of the waste at the TRU Waste Packaging Center (TWPC) will require the installation of additional equipment and capabilities to address the hazards for handling and repackaging the waste compared to typical Contact Handled (CH) TRU waste that is processed at the TWPC, including potential hydrogen accumulation in legacy 6M/2R packaging configurations, potential presence of reactive plutonium hydrides, and significant low energy gamma radiation dose rates. All of the waste is anticipated to be repackaged at the TWPC and certified for disposal at WIPP. The waste is currently packaged in multiple layers of containers which presents additional challenges for repackaging activities due to the potential for the accumulation of hydrogen gas in the container headspace in quantities than could exceed the Lower Flammability Limit (LFL). The outer container for each waste package is a stainless steel 0.21 m{sup 3} (55-gal) drum which contains either a 0.04 m{sup 3} or 0.06 m{sup 3} (10-gal or 15-gal) 6M drum. The inner 2R container in each 6M drum is ?12 cm (5 in) outside diameter x 30-36 cm (12-14 in) long and is considered to be a > 4 liter sealed container relative to TRU waste packaging criteria. Inside the 2R containers are multiple configurations of food pack cans, pipe nipples, and welded capsules. The waste contains significant quantities of high burn-up plutonium oxides and metals with a heavy weight percentage of higher atomic mass isotopes and the subsequent in-growth of significant quantities of americium. Significant low energy gamma radiation is expected to be present due to the americium in-growth. Radiation dose rates on inner containers are estimated to be 1-3 mSv/hr (100-300 mrem/hr) with an unshielded dose rate on the waste itself of over 10 mSv/hr (1 rem/hr). Additional equipment to be installed at the TWPC will include a new perma-con enclosure and a shielded/inert glovebox in the process building to repackage and stabilize the waste. All of the waste will be repackaged into Standard Pipe Overpacks. Most of the waste (21 of the 26 drums) is expected to be repackaged at the food-pack can level (i.e. the food-pack cans will not be opened). Five of the incoming waste containers are expected to be repackaged at the primary waste level. Three of the containers exceed the 200 gram Pu-239 Fissile Gram Equivalent (FGE) limit for the Standard Pipe Overpack. These three containers will be repackaged down to the primary waste level and divided into eight Standard Pipe Overpacks for shipment to WIPP. Two containers must be stabilized to eliminate any reactive plutonium hydrides that may be present. These containers will be opened in the inert, shielded glovebox, and the remaining corroded plutonium metal converted to a stable oxide form by using a 600 deg. C tube furnace with controlled oxygen feed in a helium carrier gas. The stabilized waste will then be packaged into two Standard Pipe Overpacks. Design and build out activities for the additional repackaging capabilities at the TWPC are scheduled to begin in Fiscal Year 2013 with repackaging, stabilization, and certification activities scheduled to begin in Fiscal Year 2014. Following repackaging and stabilization activities, the Standard Pipe Overpacks will be certified for disposal at WIPP utilizing Non-Destructive Examination (NDE) to verify the absence of prohibited items and Non-Destructive Assay (NDA) to verify the isotopic content under the TWPC WIPP certification program implemented by the Central Characterization Project (CCP). (authors)

Oakley, Brian; Heacker, Fred [WAI, TRU Waste Processing Center, 100 WIPP Road Lenoir City, TN 37771 (United States)] [WAI, TRU Waste Processing Center, 100 WIPP Road Lenoir City, TN 37771 (United States); McMillan, Bill [DOE, Oak Ridge Operations, Bldg. 2714, Oak Ridge, TN 37830 (United States)] [DOE, Oak Ridge Operations, Bldg. 2714, Oak Ridge, TN 37830 (United States)

2013-07-01T23:59:59.000Z

80

Porcelain enamel neutron absorbing material  

DOE Patents [OSTI]

A porcelain enamel composition as a neutron absorbing material can be prepared of a major proportion by weight of a cadmium compound and a minor proportion of compounds of boron, lithium and silicon. These compounds in the form of a porcelain enamel coating or layer on several alloys has been found to be particularly effective in enhancing the nuclear safety of equipment for use in the processing and storage of fissile material. The composition of the porcelain enamel coating can be tailored to match the coefficient of thermal expansion of the equipment to be coated and excellent coating adhesion can be achieved.

Iverson, Daniel C. (Aiken, SC)

1990-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "weapons-usable fissile materials" 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

Porcelain enamel neutron absorbing material  

DOE Patents [OSTI]

A porcelain enamel composition as a neutron absorbing material can be prepared of a major proportion by weight of a cadmium compound and a minor proportion of compound of boron, lithium and silicon. These compounds in the form of a porcelain enamel coating or layer on several alloys has been found to be particularly effective in enhancing the nuclear safety of equipment for use in the processing and storage of fissile material. The composition of the porcelain enamel coating can be tailored to match the coefficient of thermal expansion of the equipment to be coated and excellent coating adhesion can be achieved. 2 figs.

Iverson, D.C.

1987-11-20T23:59:59.000Z

82

Monte Carlo simulations of a differential die-away instrument for determination of fissile content in spent fuel assemblies  

SciTech Connect (OSTI)

The differential die-away (DDA) technique has been simulated by using the MCNPX code to quantify its capability to measure the fissile content in spent fuel assemblies, For 64 different spent fuel cases of various initial enrichment, burnup and cooling time, the count rate and signal to background ratios of the DDA system were obtained, where neutron backgrounds are mainly coming from the {sup 244}Cm of the spent fuel. To quantify the total fissile mass of spent fuel, a concept of the effective {sup 239}Pu mass was introduced by weighting the relative contribution to the signal of {sup 235}U and {sup 241}Pu compared to {sup 239}Pu and the calibration curves of DDA count rate vs. {sup 239}Pu{sub eff} were obtained by using the MCNPX code. With a deuterium-tritium (DT) neutron generator of 10{sup 9} n/s strength, signal to background ratios of sufficient magnitude are acquired for a DDA system with the spent fuel assembly in water.

Lee, Taehoon [Los Alamos National Laboratory; Menlove, Howard O [Los Alamos National Laboratory; Swinhoe, Martyn T [Los Alamos National Laboratory; Tobin, Stephen J [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

83

Gamma/neutron time-correlation for special nuclear material characterization %3CU%2B2013%3E active stimulation of highly enriched uranium.  

SciTech Connect (OSTI)

A series of simulations and experiments were undertaken to explore and evaluate the potential for a novel new technique for fissile material detection and characterization, the timecorrelated pulse-height (TCPH) method, to be used concurrent with active stimulation of potential nuclear materials. In previous work TCPH has been established as a highly sensitive method for the detection and characterization of configurations of fissile material containing Plutonium in passive measurements. By actively stimulating fission with the introduction of an external radiation source, we have shown that TCPH is also an effective method of detecting and characterizing configurations of fissile material containing Highly Enriched Uranium (HEU). The TCPH method is shown to be robust in the presence of the proper choice of external radiation source. An evaluation of potential interrogation sources is presented.

Marleau, Peter; Nowack, Aaron B.; Clarke, Shaun D. [University of Michigan; Monterial, Mateusz [University of Michigan; Paff, Marc [University of Michigan; Pozzi, Sara A. [University of Michigan

2013-09-01T23:59:59.000Z

84

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

85

Dynamical description of the moments of the energy distribution of fission fragments and scission of a fissile nucleus  

SciTech Connect (OSTI)

A multidimensional stochastic approach to fission dynamics on the basis of three-dimensional Langevin equations is applied systematically to calculating the first four moments of the energy distribution of fission fragments over a broad range of Coulomb parameter values (700 < Z{sup 2}/A{sup 1/3} < 1700). For the scission of a fissile nucleus into fragments, use was made of various criteria traditional in modern fission theory: the vanishing of the neck radius at the scission instant and the equality of the neck radius to about 0.3R{sub 0} at this instant. In calculating the energy distribution, both of the criteria used lead to a fairly good description of experimental data on the first two moments and to a satisfactory description of data on the third and fourth moments of the distribution. However, the quality of the description of available experimental data is insufficiently good for giving preference to any of these criteria. Within three-dimensional Langevin dynamics, it is shown that the vanishing-radius criterion leads to unexpectably good agreement with experimental data on the first four moments of the energy distribution. A modified version of one-body dissipation where the coefficient that takes into account the reduction of the wall-formula contribution was set to k{sub s} = 0.25 was used in the calculations.

Borunov, M. V., E-mail: bmv@opsb.ru; Nadtochy, P. N.; Adeev, G. D. [Omsk State University (Russian Federation)

2007-11-15T23:59:59.000Z

86

Angular Distributions of Fragments Originating from the Spontaneous Fission of Oriented Nuclei and Problem of the Conservation of the Spin Projection onto the Symmetry Axis of a Fissile Nucleus  

SciTech Connect (OSTI)

The concept of transition fission states, which was successfully used to describe the angular distributions of fragments for the spontaneous and low-energy induced fission of axisymmetric nuclei, proves to be correct if the spin projection onto the symmetry axis of a fissile nucleus is an integral of the motion for the external region from the descent of the fissile nucleus from the external fission barrier to the scission point. Upon heating a fissile nucleus in this region to temperatures of T {approx_equal} 1 MeV (this is predicted by many theoretical models of the fission process), the Coriolis interaction uniformly mixes the possible projections of the fissile-nucleus spin for the case of low spin values, this leading to the loss of memory about transition fission states in the asymptotic region where the angular distributions of fragments are formed. Within quantum-mechanical fission theory, which takes into account deviations from A. Bohr's formula, the angular distributions of fragments are calculated for spontaneously fissile nuclei aligned by an external magnetic field at ultralow temperatures, and it is shown that an analysis of experimental angular distributions of fragments would make it possible to solve the problem of spin-projection conservation for fissile nuclei in the external region.

Kadmensky, S.G.; Rodionova, L.V. [Voronezh State University, Universitetskaya pl. 1, Voronezh, 394693 (Russian Federation)

2005-09-01T23:59:59.000Z

87

Characterization Methodology for Decommissioning Low and Intermediate Level Fissile Nuclide Contaminated Buried Soils and Process Piping Using Photon Counting  

E-Print Network [OSTI]

of Standards and Technology NORM Technologically Enhanced Naturally Occurring Radioactive Material NPS Nominal Pipe Size NRC Nuclear Regulatory Commission ORNL Oak Ridge National Laboratory vii PDF Probability Distribution Function PVC Polyvinyl...

Pritchard, Megan L

2014-05-03T23:59:59.000Z

88

Responsible stewardship of nuclear materials  

SciTech Connect (OSTI)

The ability to tap the massive energy potential of nuclear fission was first developed as a weapon to end a terrible world war. Nuclear fission is also a virtually inexhaustible energy resource, and is the only energy supply in certain areas in Russia, Kazakhstan and elsewhere. The potential link between civilian and military applications has been and continues to be a source of concern. With the end of the Cold War, this issue has taken a dramatic turn. The U.S. and Russia have agreed to reduce their nuclear weapons stockpiles by as much as two-thirds. This will make some 100 tonnes of separated plutonium and 500 tonnes of highly enriched uranium available, in a form that is obviously directly usable for weapons. The total world inventory of plutonium is now around 1000 tonnes and is increasing at 60-70 tonnes per year. There is even more highly enriched uranium. Fortunately the correct answer to what to do with excess weapons material is also the most attractive. It should be used and reused as fuel for fast reactors. Material in use (particularly nuclear material) is very easy to monitor and control, and is quite unattractive for diversion. Active management of fissile materials not only makes a major contribution to economic stability and well-being, but also simplifies accountability, inspection and other safeguards processes; provides a revenue stream to pay for the necessary safeguards; and, most importantly, limits the prospective world inventory of plutonium to only that which is used and useful.

Hannum, W.H.

1994-10-01T23:59:59.000Z

89

Nuclear criticality safety bounding analysis for the in-tank-precipitation (ITP) process, impacted by fissile isotopic weight fractions  

SciTech Connect (OSTI)

The In-Tank Precipitation process (ITP) receives High Level Waste (HLW) supernatant liquid containing radionuclides in waste processing tank 48H. Sodium tetraphenylborate, NaTPB, and monosodium titanate (MST), NaTi{sub 2}O{sub 5}H, are added for removal of radioactive Cs and Sr, respectively. In addition to removal of radio-strontium, MST will also remove plutonium and uranium. The majority of the feed solutions to ITP will come from the dissolution of supernate that had been concentrated by evaporation to a crystallized salt form, commonly referred to as saltcake. The concern for criticality safety arises from the adsorption of U and Pt onto MST. If sufficient mass and optimum conditions are achieved then criticality is credible. The concentration of u and Pt from solution into the smaller volume of precipitate represents a concern for criticality. This report supplements WSRC-TR-93-171, Nuclear Criticality Safety Bounding Analysis For The In-Tank-Precipitation (ITP) Process. Criticality safety in ITP can be analyzed by two bounding conditions: (1) the minimum safe ratio of MST to fissionable material and (2) the maximum fissionable material adsorption capacity of the MST. Calculations have provided the first bounding condition and experimental analysis has established the second. This report combines these conditions with canyon facility data to evaluate the potential for criticality in the ITP process due to the adsorption of the fissionable material from solution. In addition, this report analyzes the potential impact of increased U loading onto MST. Results of this analysis demonstrate a greater safety margin for ITP operations than the previous analysis. This report further demonstrates that the potential for criticality in the ITP process due to adsorption of fissionable material by MST is not credible.

Bess, C.E.

1994-04-22T23:59:59.000Z

90

Fernald vacuum transfer system for uranium materials repackaging  

SciTech Connect (OSTI)

The Fernald Environmental Management Project (FEMP) is the site of a former Department of Energy (DOE) uranium processing plant. When production was halted, many materials were left in an intermediate state. Some of this product material included enriched uranium compounds that had to be repackaged for shipment of off-site storage. This paper provides an overview, technical description, and status of a new application of existing technology, a vacuum transfer system, to repackage the uranium bearing compounds for shipment. The vacuum transfer system provides a method of transferring compounds from their current storage configuration into packages that meet the Department of Transportation (DOT) shipping requirements for fissile materials. This is a necessary activity, supporting removal of nuclear materials prior to site decontamination and decommissioning, key to the Fernald site's closure process.

Kaushiva, Shirley; Weekley, Clint; Molecke, Martin; Polansky, Gary

2002-02-24T23:59:59.000Z

91

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

92

Apparatus and method for quantitative assay of samples of transuranic waste contained in barrels in the presence of matrix material  

DOE Patents [OSTI]

Apparatus and method for performing corrections for matrix material effects on the neutron measurements generated from analysis of transuranic waste drums using the differential-dieaway technique. By measuring the absorption index and the moderator index for a particular drum, correction factors can be determined for the effects of matrix materials on the ''observed'' quantity of fissile and fertile material present therein in order to determine the actual assays thereof. A barrel flux monitor is introduced into the measurement chamber to accomplish these measurements as a new contribution to the differential-dieaway technology. 9 figs.

Caldwell, J.T.; Herrera, G.C.; Hastings, R.D.; Shunk, E.R.; Kunz, W.E.

1987-08-28T23:59:59.000Z

93

Radcalc: An Analytical Tool for Shippers of Radioactive Material and Waste  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) ships radioactive materials in support of its research and development, environmental restoration, and national defense activities. The Radcalc software program assists personnel working on behalf of DOE in packaging and transportation determinations (e.g., isotopic decay, decay heat, regulatory classification, and gas generation) for shipment of radioactive materials and waste. Radcalc performs: - The U.S. Department of Transportation determinations and classifications (i.e., activity concentration for exempt material Type A or B, effective A1/A2, limited quantity, low specific activity, highway route controlled quantity, fissile quantity, fissile excepted, reportable quantity, list of isotopes required on shipping papers) - DOE calculations (i.e., transuranic waste, Pu-239 equivalent curies, fissile-gram equivalents) - The U.S. Nuclear Regulatory Commission packaging category (i.e., Category I, II, or III) - Dose-equivalent curie calculations - Radioactive decay calculations using a novel decay methodology and a decay data library of 1,867 isotopes typical of the range of materials encountered in DOE laboratory environments - Hydrogen and helium gas calculations - Pressure calculations. Radcalc is a validated and cost-effective tool to provide consistency, accuracy, reproducibility, timeliness, quality, compliance, and appropriate documentation to shippers of radioactive materials and waste at DOE facilities nationwide. Hundreds of shippers and engineers throughout the DOE Complex routinely use this software to automate various determinations and to validate compliance with the regulations. The effective use of software by DOE sites contributes toward minimizing risk involved in radioactive waste shipments and assuring the safety of workers and the public. (authors)

Kapoor, A.K. [U.S. Department of Energy, Office of Transportation, Washington, DC (United States); Stuhl, L.A. [EnergySolutions Federal Services, Inc., Richland, WA (United States)

2008-07-01T23:59:59.000Z

94

Characterization of candidate DOE sites for fabricating MOX fuel for lead assemblies  

SciTech Connect (OSTI)

The Office of Fissile Materials Disposition (MD) of the Department of Energy (DOE) is directing the program to disposition US surplus weapons-usable plutonium. For the reactor option for disposition of this surplus plutonium, MD is seeking to contract with a consortium, which would include a mixed-oxide (MOX) fuel fabricator and a commercial US reactor operator, to fabricate and burn MOX fuel in existing commercial nuclear reactors. This option would entail establishing a MOX fuel fabrication facility under the direction of the consortium on an existing DOE site. Because of the lead time required to establish a MOX fuel fabrication facility and the need to qualify the MOX fuel for use in a commercial reactor, MD is considering the early fabrication of lead assemblies (LAs) in existing DOE facilities under the technical direction of the consortium. The LA facility would be expected to produce a minimum of 1 metric ton heavy metal per year and must be operational by June 2003. DOE operations offices were asked to identify candidate sites and facilities to be evaluated for suitability to fabricate MOX fuel LAs. Savannah River Site, Argonne National Laboratory-West, Hanford, Lawrence Livermore National Laboratory, and Los Alamos National Laboratory were identified as final candidates to host the LA project. A Site Evaluation Team (SET) worked with each site to develop viable plans for the LA project. SET then characterized the suitability of each of the five plans for fabricating MOX LAs using 28 attributes and documented the characterization to aid DOE and the consortium in selecting the site for the LA project. SET concluded that each option has relative advantages and disadvantages in comparison with other options; however, each could meet the requirements of the LA project as outlined by MD and SET.

Holdaway, R.F.; Miller, J.W.; Sease, J.D.; Moses, R.J.; O`Connor, D.G. [Oak Ridge National Lab., TN (United States); Carrell, R.D. [Technical Resources International, Inc., Richland, WA (United States); Jaeger, C.D. [Sandia National Labs., Albuquerque, NM (United States); Thompson, M.L.; Strasser, A.A. [Delta-21 Resources, Inc., Oak Ridge, TN (United States)

1998-03-01T23:59:59.000Z

95

Russian-U.S. joint program on the safe management of nuclear materials  

SciTech Connect (OSTI)

The Russian-US joint program on the safety of nuclear materials was initiated in response to the 1993 Tomsk-7 accident. The bases for this program are the common technical issues confronting the US and Russia in the safe management of excess weapons grade nuclear materials. The US and Russian weapons dismantlement process is producing hundreds of tons of excess Pu and HEU fissile materials. The US is on a two path approach for disposition of excess Pu: (1) use Pu in existing reactors and/or (2) immobilize Pu in glass or ceramics followed by geologic disposal. Russian plans are to fuel reactors with excess Pu. US and Russia are both converting and blending HEU into LEU for use in existing reactors. Fissile nuclear materials storage, handling, processing, and transportation will be occurring in both countries for tens of years. A table provides a history of the major events comprising the Russian-US joint program on the safety of nuclear materials. A paper delineating program efforts was delivered at the SPECTRUM '96 conference. This paper provides an update on program activities since then.

Witmer, F.E.; Krumpe, P.F. [Dept. of Energy, Washington, DC (US); Carlson, D.D. [Sandia National Labs., Albuquerque, NM (US)] [and others

1997-12-01T23:59:59.000Z

96

Nuclear Materials Identification System (NMIS) with Gamma Spectrometry for Attributes of Pu, HEU, and Detection of HE and Chemical Agents  

SciTech Connect (OSTI)

A combined Nuclear Materials Identification System (NMIS)-gamma ray spectrometry system can be used passively to obtain the following attributes of Pu: presence, fissile mass, 240/239 ratio, and metal vs. oxide. This system can also be used with a small, portable, DT neutron generator to measure the attributes of highly enriched uranium (HEU): presence, fissile mass, enrichment, metal vs. oxide; and detect the presence of high explosives (HE). For the passive system, time-dependent coincidence distributions can be used for the presence, fissile mass, metal vs. oxide for Pu, and gamma-ray spectrometry can be used for 239/240 ratio and presence. So presence can be confirmed by two methods. For the active system with a DT neutron generator, all four attributes for both Pu and HEU can be determined from various features of the time-dependent coincidence distribution measurements for both Pu and HEU. Active gamma ray spectrometry would also give presence and 240/239 ratio for Pu, enrichment for HEU, and metal vs. oxide for both. Active gamma ray spectrometry would determine the presence of HE. The various features of time-dependent coincidence distributions and gamma ray spectrometry that determine these attributes are discussed with some examples from previous determinations.

Mihalczo, J. T.; Mattingly, J. K.; Mullens, J. A.; Neal, J. S.

2002-05-01T23:59:59.000Z

97

Atoms for peace and the nonproliferation treaty: unintended consequences  

SciTech Connect (OSTI)

In April 2009, President Obama revived nonproliferation and arms control efforts with a speech calling for the worldwide abolition of nuclear weapons. His speech correctly acknowledged the threat of nuclear terrorism and the vulnerabilities of the related unsecure nuclear materials. Unfortunately, the president did not mention and has not mentioned in any speech the threat posed by at-risk radiological materials. Nonproliferation efforts have a well documented history of focus on special nuclear materials (fissionable weapons usable materials or SNM), and other key materials (chemical and biological) and technologies for a Weapon of Mass Destruction (WMD). Such intense focus on WMD related materials/technologies is essential for international safety and security and merit continued attention and funding. However, the perception that radioactive sealed sources (sources) are of less concern than WMD is unfortunate. These perceptions are based solely on the potentially enormous and tragic consequences associated with their deliberate or accidental misuse and proliferation concerns. However, there is a documented history of overemphasis on the nuclear threat at the expense of ignoring the far more likely and also devastating chemical and biological threats. The radiological threat should not be minimized or excluded from policy discussions and decisions on these far ranging scopes of threat to the international community. Sources have a long history of use; and a wider distribution worldwide than fissile materials. Pair this with their broad ranges in isotopes/activities along with scant national and international attention and mechanisms for their safe and secure management and it is not difficult to envision a deadly threat. Arguments that minimize or divert attention away from sources may have the effect of distracting necessary policy attention on preventing/mitigating a radiological dispersal event. The terrorist attacks on 9/11 should be a clear reminder of the inherent danger of diminishing or dismissing lower-level threats in exchange for enhanced focus on high priority special nuclear materials with the basis for this emphasis being solely on the magnitude of the consequences of a single event. Mitigating all possible or likely terrorist attacks is impossible; however, weaponized sources, in the form of a radiological dispersal device, have been a declared target material of Al-Qaida. Eisenhower's Atoms for Peace initiative promoted the spread of the paradoxical beneficial yet destructive properties of the atom. Typically, the focus of nonproliferation efforts focuses on the fissile materials associated with Weapons of Mass Destruction, with less emphasis on radioactive materials that could be used for a Weapon of Mass Disruption. Most nonproliferation policy discussion involves securing or preventing the diversion of weapons grade fissile materials (uranium (U) with concentration of over 90% of the isotope {sup 235}U (HEU) and plutonium with more than 90% of the isotope {sup 239}Pu), with scant attention given to the threat posed by a prolific quantity of sources spread worldwide. Further acerbating the problem of inattention, it appears that the momentum of the continued evolution in the beneficial applications of sources will only increase in the near future. Several expert studies have demonstrated on the potentially devastating economic, psychological and public health impacts of terrorist use of a radiological dispersal or radiation emitting device (ROD/RED) in a metropolis. The development of such a weapon, from the acquisition of the radioactive material to the technical knowledge needed to fashion it into an ROD, is many orders of magnitude easier than diverting enough fissile material for and fabrication/acquisition of a nuclear weapon. Unlike nuclear weapons, worldwide, there are many well documented accounts of accidental and purposeful diversions of radioactive materials from regulatory control. As of the end of 2008, the International Atomic Energy Agency's (IAEA) Illicit Trafficking Database had logge

Streeper, Charles Blamires [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

98

Routine inspection effort required for verification of a nuclear material production cutoff convention  

SciTech Connect (OSTI)

On 27 September 1993, President Clinton proposed {open_quotes}... a multilateral convention prohibiting the production of highly enriched uranium or plutonium for nuclear explosives purposes or outside of international safeguards.{close_quotes} The UN General Assembly subsequently adopted a resolution recommending negotiation of a non-discriminatory, multilateral, and internationally and effectively verifiable treaty (hereinafter referred to as {open_quotes}the Cutoff Convention{close_quotes}) banning the production of fissile material for nuclear weapons. The matter is now on the agenda of the Conference on Disarmament, although not yet under negotiation. This accord would, in effect, place all fissile material (defined as highly enriched uranium and plutonium) produced after entry into force (EIF) of the accord under international safeguards. {open_quotes}Production{close_quotes} would mean separation of the material in question from radioactive fission products, as in spent fuel reprocessing, or enrichment of uranium above the 20% level, which defines highly enriched uranium (HEU). Facilities where such production could occur would be safeguarded to verify that either such production is not occurring or that all material produced at these facilities is maintained under safeguards.

Dougherty, D.; Fainberg, A.; Sanborn, J.; Allentuck, J.; Sun, C.

1996-11-01T23:59:59.000Z

99

Materials Scientist  

Broader source: Energy.gov [DOE]

Alternate Title(s):Materials Research Engineer; Metallurgical/Chemical Engineer; Product Development Manager;

100

Scanning of vehicles for nuclear materials  

SciTech Connect (OSTI)

Might a nuclear-armed terrorist group or state use ordinary commerce to deliver a nuclear weapon by smuggling it in a cargo container or vehicle? This delivery method would be the only one available to a sub-state actor, and it might enable a state to make an unattributed attack. Detection of a weapon or fissile material smuggled in this manner is difficult because of the large volume and mass available for shielding. Here I review methods for screening cargo containers to detect the possible presence of nuclear threats. Because of the large volume of innocent international commerce, and the cost and disruption of secondary screening by opening and inspection, it is essential that the method be rapid and have a low false-positive rate. Shielding can prevent the detection of neutrons emitted spontaneously or by induced fission. The two promising methods are muon tomography and high energy X-radiography. If they do not detect a shielded threat object they can detect the shield itself.

Katz, J. I. [Dept. Physics and McDonnell Center for the Space Sciences, Washington University, St. Louis, MO 63130 (United States)

2014-05-09T23:59:59.000Z

Note: This page contains sample records for the topic "weapons-usable fissile materials" 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

weapons material  

National Nuclear Security Administration (NNSA)

2%2A en Office of Weapons Material Protection http:nnsa.energy.govaboutusourprogramsnonproliferationprogramofficesinternationalmaterialprotectionandcooperation-1

102

THERMAL EVALUATION OF DRUM TYPE RADIOACTIVE MATERIAL PACKAGING ARRAYS IN STORAGE  

SciTech Connect (OSTI)

Drum type packages are routinely used to transport radioactive material (RAM) in the U.S. Department of Energy (DOE) complex. These packages are designed to meet the federal regulations described in 10 CFR 71.[1] In recent years, there has been a greater need to use these packagings to store the excess fissile material, especially plutonium for long term storage. While the design requirements for safe transportation of these packagings are well defined, the requirements for safe long term storage are not well established. Since the RAM contents in the packagings produce decay heat, it is important that they are stored carefully to prevent overheating of the containment vessel (CV) seals to prevent any leakage and the impact limiter to maintain the package structural integrity. This paper analyzes different storage arrays for a typical 9977 packaging for thermal considerations and makes recommendations for their safe storage under normal operating conditions.

Gupta, N

2009-04-27T23:59:59.000Z

103

Alternative technical summary report for direct disposition in deep boreholes: Direct disposal of plutonium metal/plutonium dioxide in compound canisters, Version 4.0. Fissile Materials Disposition Program  

SciTech Connect (OSTI)

This report summarizes and compares the Immobilized and Direct Beep Borehole Disposition Alternatives. The important design concepts, facility features and operational procedures are briefly described, and a discussion of the issues that affect the evaluation of each alternative against the programmatic assessment criteria that have been established for selecting the preferred alternatives for plutonium disposition.

Wijesinghe, A.M.

1996-08-23T23:59:59.000Z

104

Alternative technical summary report for immobilized disposition in deep boreholes: Immobilized disposal of plutonium in coated ceramic pellets in grout without canisters, Version 4.0. Fissile materials disposition program  

SciTech Connect (OSTI)

This paper summarizes and compares the immobilized and direct borehole disposition alternatives previously presented in the alternative technical summary. The important design concepts, facility features and operational procedures are first briefly described. This is followed by a discussion of the issues that affect the evaluation of each alternative against the programmatic assessment criteria that have been established for selecting the preferred alternatives for plutonium disposition.

Wijesinghe, A.M.

1996-08-23T23:59:59.000Z

105

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

106

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

107

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

108

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

109

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...

110

Proliferation Resistant Nuclear Reactor Fuel  

SciTech Connect (OSTI)

Global appetite for fission power is projected to grow dramatically this century, and for good reason. Despite considerable research to identify new sources of energy, fission remains the most plentiful and practical alternative to fossil fuels. The environmental challenges of fossil fuel have made the fission power option increasingly attractive, particularly as we are forced to rely on reserves in ecologically fragile or politically unstable corners of the globe. Caught between a globally eroding fossil fuel reserve as well as the uncertainty and considerable costs in the development of fusion power, most of the world will most likely come to rely on fission power for at least the remainder of the 21st century. Despite inevitable growth, fission power faces enduring challenges in sustainability and security. One of fission power's greatest hurdles to universal acceptance is the risk of potential misuse for nefarious purposes of fissionable byproducts in spent fuel, such as plutonium. With this issue in mind, we have discussed intrinsic concepts in this report that are motivated by the premise that the utility, desirability, and applicability of nuclear materials can be reduced. In a general sense, the intrinsic solutions aim to reduce or eliminate the quantity of existing weapons usable material; avoid production of new weapons-usable material through enrichment, breeding, extraction; or employ engineering solutions to make the fuel cycle less useful or more difficult for producing weapons-usable material. By their nature, these schemes require modifications to existing fuel cycles. As such, the concomitants of these modifications require engagement from the nuclear reactor and fuel-design community to fully assess their effects. Unfortunately, active pursuit of any scheme that could further complicate the spread of domestic nuclear power will probably be understandably unpopular. Nevertheless, the nonproliferation and counterterrorism issues are paramount, and we posit that the exploration, development, and implementation of intrinsic mechanisms such as discussed here are part of a balanced approach aimed at preventing the misuse of nuclear material for nuclear-energy applications.

Gray, L W; Moody, K J; Bradley, K S; Lorenzana, H E

2011-02-18T23:59:59.000Z

111

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

112

A Program to Stabilize Nuclear Materials as Managed by the Plutonium Focus Area  

SciTech Connect (OSTI)

This paper describes the program to stabilize nuclear materials, consistent with the Department of Energy Office of Environmental Management (EM) plan, Accelerating Cleanup: Paths to Closure. The program is managed by the Plutonium Stabilization and Disposition Focus Area, which defines and manages technology development programs to stabilize nuclear materials and assure their subsequent safe storage and final disposition. The scope of the Plutonium Stabilization and Disposition Focus Area (PFA) activities includes non-weapons plutonium materials, special isotopes, and other fissile materials. The PFA provides solutions to site-specific and complex wide technology issues associated with plutonium remediation, stabilization, and preparation for disposition. Our paper describes an important programmatic function of the Department of Energy nuclear materials stabilization program, including the tie-in of policy to research needs and funding for the nuclear materials disposition area. The PFA uses a rigorous systems engineering determination of technology needs and gaps, under the guidance of a Technical Advisory Panel, consisting of complex-wide experts. The Research and Development planning provides an example for other waste areas and should be of interest to Research and Development managers. The materials disposition maps developed by the PFA and described in this paper provide an evaluation of research needs, data gaps and subsequent guidance for the development of technologies for nuclear materials disposition. This paper also addresses the PFA prioritization methodology and its ability to forecast actual time to implementation.

B. Kenley (Kenley Consulting); B. Scott; B. Seidel (ANL-W); D. Knecht (LMITCO); F. Southworth; K. Osborne (DOE-ID); N. Chipman; T. Creque

1999-03-01T23:59:59.000Z

113

Some thoughts on the nonproliferation of nuclear weapons  

SciTech Connect (OSTI)

This paper discusses factors controlling the dissemination of nuclear technologies and especially fissile materials.

Krikorian N.H.; Hawkins, H.T.

1996-05-01T23:59:59.000Z

114

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

115

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

116

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

117

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

118

THE ATTRACTIVENESS OF MATERIALS IN ADVANCED NUCLEAR FUEL CYCLES FOR VARIOUS PROLIFERATION AND THEFT SCENARIOS  

SciTech Connect (OSTI)

We must anticipate that the day is approaching when details of nuclear weapons design and fabrication will become common knowledge. On that day we must be particularly certain that all special nuclear materials (SNM) are adequately accounted for and protected and that we have a clear understanding of the utility of nuclear materials to potential adversaries. To this end, this paper examines the attractiveness of materials mixtures containing SNM and alternate nuclear materials associated with the plutonium-uranium reduction extraction (Purex), uranium extraction (UREX), coextraction (COEX), thorium extraction (THOREX), and PYROX (an electrochemical refining method) reprocessing schemes. This paper provides a set of figures of merit for evaluating material attractiveness that covers a broad range of proliferant state and subnational group capabilities. The primary conclusion of this paper is that all fissile material must be rigorously safeguarded to detect diversion by a state and must be provided the highest levels of physical protection to prevent theft by subnational groups; no 'silver bullet' fuel cycle has been found that will permit the relaxation of current international safeguards or national physical security protection levels. The work reported herein has been performed at the request of the U.S. Department of Energy (DOE) and is based on the calculation of 'attractiveness levels' that are expressed in terms consistent with, but normally reserved for, the nuclear materials in DOE nuclear facilities. The methodology and findings are presented. Additionally, how these attractiveness levels relate to proliferation resistance and physical security is discussed.

Bathke, C. G.; Ebbinghaus, Bartley B.; Collins, Brian A.; Sleaford, Brad W.; Hase, Kevin R.; Robel, Martin; Wallace, R. K.; Bradley, Keith S.; Ireland, J. R.; Jarvinen, G. D.; Johnson, M. W.; Prichard, Andrew W.; Smith, Brian W.

2012-08-29T23:59:59.000Z

119

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

120

Supplement to the Surplus Plutonium Disposition Draft Environmental Impact Statement  

SciTech Connect (OSTI)

On May 22, 1997, DOE published a Notice of Intent in the Federal Register (62 Federal Register 28009) announcing its decision to prepare an environmental impact statement (EIS) that would tier from the analysis and decisions reached in connection with the ''Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic EIS (Storage and Disposition PEIS)''. ''The Surplus Plutonium Disposition Draft Environmental Impact Statement'' (SPD Draft EIS) (DOWEIS-0283-D) was prepared in accordance with NEPA and issued in July 1998. It identified the potential environmental impacts of reasonable alternatives for the proposed siting, construction, and operation of three facilities for plutonium disposition. These three facilities would accomplish pit disassembly and conversion, immobilization, and MOX fuel fabrication. For the alternatives that included MOX fuel fabrication, the draft also described the potential environmental impacts of using from three to eight commercial nuclear reactors to irradiate MOX fuel. The potential impacts were based on a generic reactor analysis that used actual reactor data and a range of potential site conditions. In May 1998, DCE initiated a procurement process to obtain MOX fuel fabrication and reactor irradiation services. The request for proposals defined limited activities that may be performed prior to issuance of the SPD EIS Record of Decision (ROD) including non-site-specific work associated with the development of the initial design for the MOX fuel fabrication facility, and plans (paper studies) for outreach, long lead-time procurements, regulatory management, facility quality assurance, safeguards, security, fuel qualification, and deactivation. No construction on the proposed MOX facility would begin before an SPD EIS ROD is issued. In March 1999, DOE awarded a contract to Duke Engineering & Services; COGEMA, Inc.; and Stone & Webster (known as DCS) to provide the requested services. The procurement process included the environmental review specified in DOE's NEPA regulations in 10 CFR 1021.216. The six reactors selected are Catawba Nuclear Station Units 1 and 2 in South Carolina McGuire Nuclear Station Units 1 and 2 in North Carolina, and North Anna Power Station Units 1 and 2 in Virginia. The Supplement describes the potential environmental impacts of using MOX fuel in these six specific reactors named in the DCS proposal as well as other program changes made since the SPD Draft EIS was published.

N /A

1999-05-14T23:59:59.000Z

Note: This page contains sample records for the topic "weapons-usable fissile materials" 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

LIFE Materials: Phase Formation and Transformations in Transmutation Fuel Materials for the LIFE Engine Part I - Path Forward Volume 3  

SciTech Connect (OSTI)

The current specifications of the LLNL fusion-fission hybrid proposal, namely LIFE, impose severe constraints on materials, and in particular on the nuclear fissile or fertile nuclear fuel and its immediate environment. This constitutes the focus of the present report with special emphasis on phase formation and phase transformations of the transmutation fuel and their consequences on particle and pebble thermal, chemical, and mechanical integrities. We first review the work that has been done in recent years to improve materials properties under the Gen-IV project, and with in particular applications to HTGR and MSR, and also under GNEP and AFCI in the USA. Our goal is to assess the nuclear fuel options that currently exist together with their issues. Among the options, it is worth mentioning TRISO, IMF, and molten salts. The later option will not be discussed in details since an entire report (Volume 8 - Molten-salt Fuels) is dedicated to it. Then, in a second part, with the specific LIFE specifications in mind, the various fuel options with their most critical issues are revisited with a path forward for each of them in terms of research, both experimental and theoretical. Since LIFE is applicable to very high burn-up of various fuels, distinctions will be made depending on the mission, i.e., energy production or incineration. Finally a few conclusions are drawn in terms of the specific needs for integrated materials modeling and the in depth knowledge on time-evolution thermo-chemistry that controls and drastically affects the performance of the nuclear materials and their immediate environment. Although LIFE demands materials that very likely have not yet been fully optimized, the challenges are not insurmountable, and a well concerted experimental-modeling effort should lead to dramatic advances that should well serve other fission programs such as Gen-IV, GNEP, AFCI as well as the international fusion program, ITER.

Turchi, P A; Kaufman, L; Fluss, M

2008-12-19T23:59:59.000Z

122

Materials Science & Tech Division | Advanced Materials | ORNL  

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

Materials Science and Technology SHARE Materials Science and Technology Division The Materials Science and Technology Division is unique within the Department of Energy (DOE)...

123

Nuclear reactor fissile isotopes antineutrino spectra  

E-Print Network [OSTI]

Positron spectrum from inverse beta decay reaction on proton was measured in 1988-1990 as a result of neutrino exploration experiment. The measured spectrum has the largest statistics and lowest energy threshold between other neutrino experiments made that time at nuclear reactors. On base of the positron spectrum the standard antineutrino spectrum for typical reactor fuel composition was restored. In presented analysis the partial spectra forming this standard spectrum were extracted using specific method. They could be used for neutrino experiments data analysis made at any fuel composition of reactor core.

V. Sinev

2012-07-30T23:59:59.000Z

124

The Attractiveness of Materials in Advanced Nuclear Fuel Cycles for Various Proliferation and Theft Scenarios  

SciTech Connect (OSTI)

This paper is an extension to earlier studies1,2 that examined the attractiveness of materials mixtures containing special nuclear materials (SNM) and alternate nuclear materials (ANM) associated with the PUREX, UREX, COEX, THOREX, and PYROX reprocessing schemes. This study extends the figure of merit (FOM) for evaluating attractiveness to cover a broad range of proliferant state and sub-national group capabilities. The primary conclusion of this study is that all fissile material needs to be rigorously safeguarded to detect diversion by a state and provided the highest levels of physical protection to prevent theft by sub-national groups; no silver bullet has been found that will permit the relaxation of current international safeguards or national physical security protection levels. This series of studies has been performed at the request of the United States Department of Energy (DOE) and is based on the calculation of "attractiveness levels" that are expressed in terms consistent with, but normally reserved for nuclear materials in DOE nuclear facilities.3 The expanded methodology and updated findings are presented. Additionally, how these attractiveness levels relate to proliferation resistance and physical security are discussed.

Bathke, C. G.; Wallace, R. K.; Ireland, J. R.; Johnson, M. W.; Hase, Kevin R.; Jarvinen, G. D.; Ebbinghaus, B. B.; Sleaford, Brad W.; Bradley, Keith S.; Collins, Brian A.; Smith, Brian W.; Prichard, Andrew W.

2010-09-01T23:59:59.000Z

125

Casting materials  

DOE Patents [OSTI]

A foam material comprises a liquid polymer and a liquid isocyanate which is mixed to make a solution that is poured, injected or otherwise deposited into a corresponding mold. A reaction from the mixture of the liquid polymer and liquid isocyanate inside the mold forms a thermally collapsible foam structure having a shape that corresponds to the inside surface configuration of the mold and a skin that is continuous and unbroken. Once the reaction is complete, the foam pattern is removed from the mold and may be used as a pattern in any number of conventional casting processes.

Chaudhry, Anil R. (Xenia, OH); Dzugan, Robert (Cincinnati, OH); Harrington, Richard M. (Cincinnati, OH); Neece, Faurice D. (Lyndurst, OH); Singh, Nipendra P. (Pepper Pike, OH)

2011-06-14T23:59:59.000Z

126

Reference Material  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared at 278, 298,NIST 800-53Reference Materials There are a variety of

127

Materials Science  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: VegetationEquipment Surfaces andMapping the Nanoscale LandscapeImports 5.90 4.86(NHMFL)X-RayMaterials

128

Simulated Verification of Fuel Element Inventory in a Small Reactor Core Using the Nuclear Materials Identification System (NMIS)  

SciTech Connect (OSTI)

The International Panel on Climate Change projects that by 2050 the world energy demand may double. Although the primary focus for new nuclear power plants in industrialized nations is on large plants in the 1000-1600 MWe range, there is an increasing demand for small and medium reactors (SMRs). About half of the innovative SMR concepts are for small (<300 MWe) reactors with a 5-30 year life without on-site refueling. This type of reactor is also known as a battery-type reactor. These reactors are particularly attractive to countries with small power grids and for non-electrical purposes such as heating, hydrogen production, and seawater desalination. Traditionally, this type of reactor has been used in a nautical propulsion role. This type of reactor is designed as a permanently sealed unit to prevent the diversion of the uranium in the core by the user. However, after initial fabrication it will be necessary to verify that the newly fabricated reactor core contains the quantity of uranium that initially entered the fuel fabrication plant. In most instances, traditional inspection techniques can be used to perform this verification, but in certain situations the core design will be considered sensitive. Non-intrusive verification techniques must be utilized in these situations. The Nuclear Materials Identification System (NMIS) with imaging uses active interrogation and a fast time correlation processor to characterize fissile material. The MCNP-PoliMi computer code was used to simulate NMIS measurements of a small, sealed reactor core. Because most battery-type reactor designs are still in the early design phase, a more traditional design based on a Russian icebreaker core was used in the simulations. These simulations show how the radiography capabilities of the NMIS could be used to detect the diversion of fissile material by detecting void areas in the assembled core where fuel elements have been removed.

Grogan, Brandon R [ORNL; Mihalczo, John T [ORNL

2009-01-01T23:59:59.000Z

129

Photovoltaic Materials  

SciTech Connect (OSTI)

The goal of the current project was to help make the US solar industry a world leader in the manufacture of thin film photovoltaics. The overall approach was to leverage ORNLs unique characterization and processing technologies to gain a better understanding of the fundamental challenges for solar cell processing and apply that knowledge to targeted projects with industry members. ORNL has the capabilities in place and the expertise required to understand how basic material properties including defects, impurities, and grain boundaries affect the solar cell performance. ORNL also has unique processing capabilities to optimize the manufacturing process for fabrication of high efficiency and low cost solar cells. ORNL recently established the Center for Advanced Thin-film Systems (CATS), which contains a suite of optical and electrical characterization equipment specifically focused on solar cell research. Under this project, ORNL made these facilities available to industrial partners who were interested in pursuing collaborative research toward the improvement of their product or manufacturing process. Four specific projects were pursued with industrial partners: Global Solar Energy is a solar industry leader in full scale production manufacturing highly-efficient Copper Indium Gallium diSelenide (CIGS) thin film solar material, cells and products. ORNL worked with GSE to develop a scalable, non-vacuum, solution technique to deposit amorphous or nanocrystalline conducting barrier layers on untextured stainless steel substrates for fabricating high efficiency flexible CIGS PV. Ferro Corporations Electronic, Color and Glass Materials (ECGM) business unit is currently the worlds largest supplier of metallic contact materials in the crystalline solar cell marketplace. Ferros ECGM business unit has been the world's leading supplier of thick film metal pastes to the crystalline silicon PV industry for more than 30 years, and has had operational cells and modules in the field for 25 years. Under this project, Ferro leveraged world leading analytical capabilities at ORNL to characterize the paste-to-silicon interface microstructure and develop high efficiency next generation contact pastes. Ampulse Corporation is developing a revolutionary crystalline-silicon (c-Si) thin-film solar photovoltaic (PV) technology. Utilizing uniquely-textured substrates and buffer materials from the Oak Ridge National Laboratory (ORNL), and breakthroughs in Hot-Wire Chemical Vapor Deposition (HW-CVD) techniques in epitaxial silicon developed at the National Renewable Energy Laboratory (NREL), Ampulse is creating a solar technology that is tunable in silicon thickness, and hence in efficiency and economics, to meet the specific requirements of multiple solar PV applications. This project focused on the development of a high rate deposition process to deposit Si, Ge, and Si1-xGex films as an alternate to hot-wire CVD. Mossey Creek Solar is a start-up company with great expertise in the solar field. The primary interest is to create and preserve jobs in the solar sector by developing high-yield, low-cost, high-efficiency solar cells using MSC-patented and -proprietary technologies. The specific goal of this project was to produce large grain formation in thin, net-shape-thickness mc-Si wafers processed with high-purity silicon powder and ORNL's plasma arc lamp melting without introducing impurities that compromise absorption coefficient and carrier lifetime. As part of this project, ORNL also added specific pieces of equipment to enhance our ability to provide unique insight for the solar industry. These capabilities include a moisture barrier measurement system, a combined physical vapor deposition and sputtering system dedicated to cadmium-containing deposits, adeep level transient spectroscopy system useful for identifying defects, an integrating sphere photoluminescence system, and a high-speed ink jet printing system. These tools were combined with others to study the effect of defects on the performance of crystalline silicon and

Duty, C.; Angelini, J.; Armstrong, B.; Bennett, C.; Evans, B.; Jellison, G. E.; Joshi, P.; List, F.; Paranthaman, P.; Parish, C.; Wereszczak, A.

2012-10-15T23:59:59.000Z

130

Critical Materials Institute  

ScienceCinema (OSTI)

Ames Laboratory Director Alex King talks about the goals of the Critical Materials Institute in diversifying the supply of critical materials, developing substitute materials, developing tools and techniques for recycling critical materials, and forecasting materials needs to avoid future shortages.

Alex King

2013-06-05T23:59:59.000Z

131

Incorporation of Integral Fuel Burnable Absorbers Boron and Gadolinium into Zirconium-Alloy Fuel Clad Material  

SciTech Connect (OSTI)

Long-lived fuels require the use of higher enrichments of 235U or other fissile materials. Such high levels of fissile material lead to excessive fuel activity at the beginning of life. To counteract this excessive activity, integral fuel burnable absorbers (IFBA) are added to some rods in the fuel assembly. The two commonly used IFBA elements are gadolinium, which is added as gadolinium-oxide to the UO2 powder, and boron, which is applied as a zirconium-diboride coating on the UO2 pellets using plasma spraying or chemical vapor deposition techniques. The incorporation of IFBA into the fuel has to be performed in a nuclear-regulated facility that is physically separated from the main plant. These operations tend to be very costly because of their small volume and can add from 20 to 30% to the manufacturing cost of the fuel. Other manufacturing issues that impact cost and performance are maintaining the correct levels of dosing, the reduction in fuel melting point due to gadolinium-oxide additions, and parasitic neutron absorption at fuel's end-of-life. The goal of the proposed research is to develop an alternative approach that involves incorporation of boron or gadolinium into the outer surface of the fuel cladding material rather than as an additive to the fuel pellets. This paradigm shift will allow for the introduction of the IFBA in a non-nuclear regulated environment and will obviate the necessity of additional handling and processing of the fuel pellets. This could represent significant cost savings and potentially lead to greater reproducibility and control of the burnable fuel in the early stages of the reactor operation. The surface alloying is being performed using the IBEST (Ion Beam Surface Treatment) process developed at Sandia National Laboratories. IBEST involves the delivery of energetic ion beam pulses onto the surface of a material, near-surface melting, and rapid solidification. The non-equilibrium nature of such processing allows for surface alloying well in excess of the thermodynamically dictated solubility limits, an effect that is particularly relevant to this research due to the negligible solubility of boron and gadolinium in zirconium. University of Wisconsin is performing the near surface materials characterization and analysis, aiding Sandia in process optimization, and promoting educational activities. Westinghouse is performing process manufacturability and scale-up analysis and is performing autoclave testing of the surface treated samples. The duration of this NERI project is 2 years, from 9/2002 to 9/2004.

Sridharan, K.; Renk, T.J.; Lahoda, E.J.; Corradini, M.L

2004-12-14T23:59:59.000Z

132

Terminating Safeguards on Excess Special Nuclear Material: Defense TRU Waste Clean-up and Nonproliferation - 12426  

SciTech Connect (OSTI)

The Department of Energy (DOE) and the National Nuclear Security Administration (NNSA) manages defense nuclear material that has been determined to be excess to programmatic needs and declared waste. When these wastes contain plutonium, they almost always meet the definition of defense transuranic (TRU) waste and are thus eligible for disposal at the Waste Isolation Pilot Plant (WIPP). The DOE operates the WIPP in a manner that physical protections for attractiveness level D or higher special nuclear material (SNM) are not the normal operating condition. Therefore, there is currently a requirement to terminate safeguards before disposal of these wastes at the WIPP. Presented are the processes used to terminate safeguards, lessons learned during the termination process, and how these approaches might be useful for future defense TRU waste needing safeguards termination prior to shipment and disposal at the WIPP. Also described is a new criticality control container, which will increase the amount of fissile material that can be loaded per container, and how it will save significant taxpayer dollars. Retrieval, compliant packaging and shipment of retrievably stored legacy TRU waste has dominated disposal operations at WIPP since it began operations 12 years ago. But because most of this legacy waste has successfully been emplaced in WIPP, the TRU waste clean-up focus is turning to newly-generated TRU materials. A major component will be transuranic SNM, currently managed in safeguards-protected vaults around the weapons complex. As DOE and NNSA continue to consolidate and shrink the weapons complex footprint, it is expected that significant quantities of transuranic SNM will be declared surplus to the nation's needs. Safeguards termination of SNM varies due to the wide range of attractiveness level of the potential material that may be directly discarded as waste. To enhance the efficiency of shipping waste with high TRU fissile content to WIPP, DOE designed an over-pack container, similar to the pipe component, called the criticality control over-pack, which will significantly enhance the efficiency of disposal. Hundreds of shipments of transuranic SNM, suitably packaged to meet WIPP waste acceptance criteria and with safeguards terminated have been successfully emplaced at WIPP (primarily from the Rocky Flats site clean-up) since WIPP opened. DOE expects that thousands more may eventually result from SNM consolidation efforts throughout the weapons complex. (authors)

Hayes, Timothy [Los Alamos National Laboratory, Carlsbad Operations Group (United States); Nelson, Roger [Department Of Energy, Carlsbad Operations Office (United States)

2012-07-01T23:59:59.000Z

133

MATERIALS MANAGEMENT MATERIALS MANAGEMENT -INVENTORY CONTROL  

E-Print Network [OSTI]

MATERIALS MANAGEMENT MATERIALS MANAGEMENT - INVENTORY CONTROL Record of Property Transferred from ______ ___________________________________ 2. DEAN (If Applies) ______ ___________________________________ 5. UNIVERSITY DIRECTOR OF MATERIALS MANAGEMENT ______ ___________________________________ 3. HOSPITAL DIRECTOR (If Applies) ______ IF YOU NEED

Oliver, Douglas L.

134

Gas storage materials, including hydrogen storage materials  

DOE Patents [OSTI]

A material for the storage and release of gases comprises a plurality of hollow elements, each hollow element comprising a porous wall enclosing an interior cavity, the interior cavity including structures of a solid-state storage material. In particular examples, the storage material is a hydrogen storage material, such as a solid state hydride. An improved method for forming such materials includes the solution diffusion of a storage material solution through a porous wall of a hollow element into an interior cavity.

Mohtadi, Rana F; Wicks, George G; Heung, Leung K; Nakamura, Kenji

2014-11-25T23:59:59.000Z

135

Gas storage materials, including hydrogen storage materials  

DOE Patents [OSTI]

A material for the storage and release of gases comprises a plurality of hollow elements, each hollow element comprising a porous wall enclosing an interior cavity, the interior cavity including structures of a solid-state storage material. In particular examples, the storage material is a hydrogen storage material such as a solid state hydride. An improved method for forming such materials includes the solution diffusion of a storage material solution through a porous wall of a hollow element into an interior cavity.

Mohtadi, Rana F; Wicks, George G; Heung, Leung K; Nakamura, Kenji

2013-02-19T23:59:59.000Z

136

Functional Materials for Energy | Advanced Materials | ORNL  

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

Energy Storage Fuel Cells Thermoelectrics Separations Materials Catalysis Sensor Materials Polymers and Composites Carbon Fiber Related Research Chemistry and Physics at...

137

DEVELOPMENT OF A NEW TYPE A(F)RADIOACTIVE MATERIAL PACKAGING FOR THE DEPARTMENT OF ENERGY  

SciTech Connect (OSTI)

In a coordinated effort, the Department of Transportation (DOT) and Nuclear Regulatory Commission (NRC) proposed the elimination of the Specification Packaging from 49 CFR 173.[1] In accordance with the Federal Register, issued on October 1, 2004, new fabrication of Specification Packages would no longer be authorized. In accordance with the NRC final rulemaking published January 26, 2004, Specification Packagings are mandated by law to be removed from service no later than October 1, 2008. This coordinated effort and resulting rulemaking initiated a planned phase out of Specification Type B and Type A fissile (F) material transportation packages within the Department of Energy (DOE) and its subcontractors. One of the Specification Packages affected by this regulatory change is the UN1A2 Specification Package, per DOT 49 CFR 173.417(a)(6). To maintain continuing shipments of DOE materials currently transported in UN1A2 Specification Package after the existing authorization expires, a replacement Type A(F) material packaging design is under development by the Savannah River National Laboratory. This paper presents a summary of the prototype design effort and testing of the new Type A(F) Package development for the DOE. This paper discusses the progress made in the development of a Type A Fissile Packaging to replace the expiring 49 CFR UN1A2 Specification Fissile Package. The Specification Package was mostly a single-use waste disposal container. The design requirements and authorized radioactive material contents of the UN1A2 Specification Package were defined in 49 CFR. A UN1A2 Specification Package was authorized to ship up to 350 grams of U-235 in any enrichment and in any non-pyrophoric form. The design was specified as a 55-gallon 1A2 drum overpack with a body constructed from 18 gauge steel with a 16 gauge drum lid. Drum closure was specified as a standard 12-gauge ring closure. The inner product container size was not specified but was listed as any container that met Specification 7A requirements per 49 CFR 178.350. Specification 7A containers were required to withstand Type A packaging tests required by 49CFR173.465 with compliance demonstrated through testing, analysis or similarity to other containers. The maximum weight of the 7A product container, the radioactive content, and any internal packaging was limited to 200 lbs. The total gross weight for the UN1A2 Specification Package was limited to 350 lbs. No additional restrictions were applied. Authorization for use did not require the UN1A2 Specification Package to be tested to the Normal Conditions of Transport (NCT) and Hypothetical Accident Conditions (HAC) required for performance based, Type A(F) packages certified by the NRC or DOE. The Type A(F) Packaging design discussed in this paper is required to be in compliance with the regulatory safety requirements defined in Code of Federal Regulations (CFR) 10 CFR 71.41 through 71.47 and 10 CFR71.71. Sub-criticality of content must be maintained under the Hypothetical Accident Conditions specified under 10 CFR71.73. These federal regulations, and other applicable DOE Orders and Guides, govern design requirements for a Type A(F) package. Type A(F) packages with less than an A2 quantity of radioactive material are not required to have a leak testable boundary. With this exception a Type A(F) package design is subject to the same test requirements set forth for the design of a performance based Type B packaging.

Blanton, P.; Eberl, K.

2008-09-14T23:59:59.000Z

138

Materials Project: A Materials Genome Approach  

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

Technological innovation - faster computers, more efficient solar cells, more compact energy storage - is often enabled by materials advances. Yet, it takes an average of 18 years to move new materials discoveries from lab to market. This is largely because materials designers operate with very little information and must painstakingly tweak new materials in the lab. Computational materials science is now powerful enough that it can predict many properties of materials before those materials are ever synthesized in the lab. By scaling materials computations over supercomputing clusters, this project has computed some properties of over 80,000 materials and screened 25,000 of these for Li-ion batteries. The computations predicted several new battery materials which were made and tested in the lab and are now being patented. By computing properties of all known materials, the Materials Project aims to remove guesswork from materials design in a variety of applications. Experimental research can be targeted to the most promising compounds from computational data sets. Researchers will be able to data-mine scientific trends in materials properties. By providing materials researchers with the information they need to design better, the Materials Project aims to accelerate innovation in materials research.[copied from http://materialsproject.org/about] You will be asked to register to be granted free, full access.

Ceder, Gerbrand (MIT); Persson, Kristin (LBNL)

139

MATERIALS MANAGEMENT MATERIALS MANAGEMENT -INVENTORY CONTROL  

E-Print Network [OSTI]

MATERIALS MANAGEMENT MATERIALS MANAGEMENT - INVENTORY CONTROL NOTICE OF DESIGNATED DEPARTMENTAL OF MATERIALS MANAGEMENT ______ FURTHER INSTRUCTIONS 1. Include a copy of any relevant documents. 2. Item MATERIALS COORDINATOR IC-8 Mail, Fax or PDF the entire package to: MC 2010 Fax: 679-4240 REFERENCE # DMC

Oliver, Douglas L.

140

Method for forming materials  

DOE Patents [OSTI]

A material-forming tool and a method for forming a material are described including a shank portion; a shoulder portion that releasably engages the shank portion; a pin that releasably engages the shoulder portion, wherein the pin defines a passageway; and a source of a material coupled in material flowing relation relative to the pin and wherein the material-forming tool is utilized in methodology that includes providing a first material; providing a second material, and placing the second material into contact with the first material; and locally plastically deforming the first material with the material-forming tool so as mix the first material and second material together to form a resulting material having characteristics different from the respective first and second materials.

Tolle, Charles R. (Idaho Falls, ID); Clark, Denis E. (Idaho Falls, ID); Smartt, Herschel B. (Idaho Falls, ID); Miller, Karen S. (Idaho Falls, ID)

2009-10-06T23:59:59.000Z

Note: This page contains sample records for the topic "weapons-usable fissile materials" 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

Transporting particulate material  

DOE Patents [OSTI]

A material transporting system comprises a material transporting apparatus (100) including a material transporting apparatus hopper structure (200, 202), which comprises at least one rotary transporting apparatus; a stationary hub structure (900) constraining and assisting the at least one rotary transporting apparatus; an outlet duct configuration (700) configured to permit material to exit therefrom and comprising at least one diverging portion (702, 702'); an outlet abutment configuration (800) configured to direct material to the outlet duct configuration; an outlet valve assembly from the material transporting system venting the material transporting system; and a moving wall configuration in the material transporting apparatus capable of assisting the material transporting apparatus in transporting material in the material transporting system. Material can be moved from the material transporting apparatus hopper structure to the outlet duct configuration through the at least one rotary transporting apparatus, the outlet abutment configuration, and the outlet valve assembly.

Aldred, Derek Leslie (North Hollywood, CA); Rader, Jeffrey A. (North Hollywood, CA); Saunders, Timothy W. (North Hollywood, CA)

2011-08-30T23:59:59.000Z

142

Definition of Small Gram Quantity Contents for Type B Radioactive Material Transportation Packages: Activity-Based Content Limitations  

SciTech Connect (OSTI)

Since the 1960's, the Department of Transportation Specification (DOT Spec) 6M packages have been used extensively for transportation of Type B quantities of radioactive materials between Department of Energy (DOE) facilities, laboratories, and productions sites. However, due to the advancement of packaging technology, the aging of the 6M packages, and variability in the quality of the packages, the DOT implemented a phased elimination of the 6M specification packages (and other DOT Spec packages) in favor of packages certified to meet federal performance requirements. DOT issued the final rule in the Federal Register on October 1, 2004 requiring that use of the DOT Specification 6M be discontinued as of October 1, 2008. A main driver for the change was the fact that the 6M specification packagings were not supported by a Safety Analysis Report for Packaging (SARP) that was compliant with Title 10 of the Code of Federal Regulations part 71 (10 CFR 71). Therefore, materials that would have historically been shipped in 6M packages are being identified as contents in Type B (and sometimes Type A fissile) package applications and addenda that are to be certified under the requirements of 10 CFR 71. The requirements in 10 CFR 71 include that the Safety Analysis Report for Packaging (SARP) must identify the maximum radioactivity of radioactive constituents and maximum quantities of fissile constituents (10 CFR 71.33(b)(1) and 10 CFR 71.33(b)(2)), and that the application (i.e., SARP submittal or SARP addendum) demonstrates that the external dose rate (due to the maximum radioactivity of radioactive constituents and maximum quantities of fissile constituents) on the surface of the packaging (i.e., package and contents) not exceed 200 mrem/hr (10 CFR 71.35(a), 10 CFR 71.47(a)). It has been proposed that a 'Small Gram Quantity' of radioactive material be defined, such that, when loaded in a transportation package, the dose rates at external points of an unshielded packaging not exceed the regulatory limits prescribed by 10 CFR 71 for non-exclusive shipments. The mass of each radioisotope presented in this paper is limited by the radiation dose rate on the external surface of the package, which per the regulatory limit should not exceed 200 mrem/hr. The results presented are a compendium of allowable masses of a variety of different isotopes (with varying impurity levels of beryllium in some of the actinide isotopes) that, when loaded in an unshielded packaging, do not result in an external dose rate on the surface of the package that exceeds 190 mrem/hr (190 mrem/hr was chosen to provide 5% conservatism relative to the regulatory limit). These mass limits define the term 'Small Gram Quantity' (SGQ) contents in the context of radioactive material transportation packages. The term SGQ is isotope-specific and pertains to contents in radioactive material transportation packages that do not require shielding and still satisfy the external dose rate requirements. Since these calculated mass limits are for contents without shielding, they are conservative for packaging materials that provide some limited shielding or if the contents are placed into a shielded package. The isotopes presented in this paper were chosen as the isotopes that Department of Energy (DOE) sites most likely need to ship. Other more rarely shipped isotopes, along with industrial and medical isotopes, are planned to be included in subsequent extensions of this work.

Sitaraman, S; Kim, S; Biswas, D; Hafner, R; Anderson, B

2010-10-27T23:59:59.000Z

143

Nanostructured magnetic materials  

E-Print Network [OSTI]

Magnetism and Magnetic Materials Conference, Atlanta, GA (Nanostructured Magnetic Materials by Keith T. Chan Doctor ofinduced by a Si-based material occurs at a Si/Ni interface

Chan, Keith T.

2011-01-01T23:59:59.000Z

144

MATERIALS TRANSFER AGREEMENT  

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

MTAXX-XXX 1 MATERIAL TRANSFER AGREEMENT for Manufacturing Demonstration Facility and Carbon Fiber Technology Facility In order for the RECIPIENT to obtain materials, the RECIPIENT...

145

battery materials | EMSL  

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

battery materials battery materials Leads No leads are available at this time. Modeling Interfacial Glass-Water Reactions: Recent Advances and Current Limitations. Abstract: The...

146

Energy Materials & Processes | EMSL  

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

in catalysts and energy materials needed to design new materials and systems for sustainable energy applications. By facilitating the development and rapid dissemination...

147

The Complete Burning of Weapons Grade Plutonium and Highly Enriched Uranium with (Laser Inertial Fusion-Fission Energy) LIFE Engine  

SciTech Connect (OSTI)

The National Ignition Facility (NIF) project, a laser-based Inertial Confinement Fusion (ICF) experiment designed to achieve thermonuclear fusion ignition and burn in the laboratory, is under construction at the Lawrence Livermore National Laboratory (LLNL) and will be completed in April of 2009. Experiments designed to accomplish the NIF's goal will commence in late FY2010 utilizing laser energies of 1 to 1.3 MJ. Fusion yields of the order of 10 to 20 MJ are expected soon thereafter. Laser initiated fusion-fission (LIFE) engines have now been designed to produce nuclear power from natural or depleted uranium without isotopic enrichment, and from spent nuclear fuel from light water reactors without chemical separation into weapons-attractive actinide streams. A point-source of high-energy neutrons produced by laser-generated, thermonuclear fusion within a target is used to achieve ultra-deep burn-up of the fertile or fissile fuel in a sub-critical fission blanket. Fertile fuels including depleted uranium (DU), natural uranium (NatU), spent nuclear fuel (SNF), and thorium (Th) can be used. Fissile fuels such as low-enrichment uranium (LEU), excess weapons plutonium (WG-Pu), and excess highly-enriched uranium (HEU) may be used as well. Based upon preliminary analyses, it is believed that LIFE could help meet worldwide electricity needs in a safe and sustainable manner, while drastically shrinking the nation's and world's stockpile of spent nuclear fuel and excess weapons materials. LIFE takes advantage of the significant advances in laser-based inertial confinement fusion that are taking place at the NIF at LLNL where it is expected that thermonuclear ignition will be achieved in the 2010-2011 timeframe. Starting from as little as 300 to 500 MW of fusion power, a single LIFE engine will be able to generate 2000 to 3000 MWt in steady state for periods of years to decades, depending on the nuclear fuel and engine configuration. Because the fission blanket in a fusion-fission hybrid system is subcritical, a LIFE engine can burn any fertile or fissile nuclear material, including unenriched natural or depleted U and SNF, and can extract a very high percentage of the energy content of its fuel resulting in greatly enhanced energy generation per metric ton of nuclear fuel, as well as nuclear waste forms with vastly reduced concentrations of long-lived actinides. LIFE engines could thus provide the ability to generate vast amounts of electricity while greatly reducing the actinide content of any existing or future nuclear waste and extending the availability of low cost nuclear fuels for several thousand years. LIFE also provides an attractive pathway for burning excess weapons Pu to over 99% FIMA (fission of initial metal atoms) without the need for fabricating or reprocessing mixed oxide fuels (MOX). Because of all of these advantages, LIFE engines offer a pathway toward sustainable and safe nuclear power that significantly mitigates nuclear proliferation concerns and minimizes nuclear waste. An important aspect of a LIFE engine is the fact that there is no need to extract the fission fuel from the fission blanket before it is burned to the desired final level. Except for fuel inspection and maintenance process times, the nuclear fuel is always within the core of the reactor and no weapons-attractive materials are available outside at any point in time. However, an important consideration when discussing proliferation concerns associated with any nuclear fuel cycle is the ease with which reactor fuel can be converted to weapons usable materials, not just when it is extracted as waste, but at any point in the fuel cycle. Although the nuclear fuel remains in the core of the engine until ultra deep actinide burn up is achieved, soon after start up of the engine, once the system breeds up to full power, several tons of fissile material is present in the fission blanket. However, this fissile material is widely dispersed in millions of fuel pebbles, which can be tagged as individual accountable items, and thus made difficult to diver

Farmer, J C; Diaz de la Rubia, T; Moses, E

2008-12-23T23:59:59.000Z

148

Phase Formation and Transformations in Transmutation Fuel Materials for the LIFE Engine Part I - Path Forward  

SciTech Connect (OSTI)

The current specifications of the LLNL fusion-fission hybrid proposal, namely LIFE, impose severe constraints on materials, and in particular on the nuclear fissile or fertile nuclear fuel and its immediate environment. This constitutes the focus of the present report with special emphasis on phase formation and phase transformations of the transmutation fuel and their consequences on particle and pebble thermal, chemical and mechanical integrities. We first review the work that has been done in recent years to improve materials properties under the Gen-IV project, and with in particular applications to HTGR and MSR, and also under GNEP and AFCI in the USA. Our goal is to assess the nuclear fuel options that currently exist together with their issues. Among the options, it is worth mentioning TRISO, IMF, and molten salts. The later option will not be discussed in details since an entire report is dedicated to it. Then, in a second part, with the specific LIFE specifications in mind, the various fuel options with their most critical issues are revisited with a path forward for each of them in terms of research, both experimental and theoretical. Since LIFE is applicable to very high burn-up of various fuels, distinctions will be made depending on the mission, i.e., energy production or incineration. Finally a few conclusions are drawn in terms of the specific needs for integrated materials modeling and the in depth knowledge on time-evolution thermochemistry that controls and drastically affects the performance of the nuclear materials and their immediate environment. Although LIFE demands materials that very likely have not yet been fully optimized, the challenge are not insurmountable and a well concerted experimental-modeling effort should lead to dramatic advances that should well serve other fission programs such as Gen-IV, GNEP, AFCI as well as the international fusion program, ITER.

Turchi, P E; Kaufman, L; Fluss, M J

2008-11-10T23:59:59.000Z

149

Coated ceramic breeder materials  

DOE Patents [OSTI]

A breeder material for use in a breeder blanket of a nuclear reactor is disclosed. The breeder material comprises a core material of lithium containing ceramic particles which has been coated with a neutron multiplier such as Be or BeO, which coating has a higher thermal conductivity than the core material.

Tam, Shiu-Wing (Downers Grove, IL); Johnson, Carl E. (Elk Grove, IL)

1987-01-01T23:59:59.000Z

150

HAZARDOUS MATERIALS EMERGENCY RESPONSE  

E-Print Network [OSTI]

ANNEX Q HAZARDOUS MATERIALS EMERGENCY RESPONSE #12;ANNEX Q - HAZARDOUS MATERIALS EMERGENCY RESPONSE 03/10/2014 v.2.0 Page Q-1 PROMULGATION STATEMENT Annex Q: Hazardous Materials Emergency Response, and contents within, is a guide to how the University conducts a response specific to a hazardous materials

151

UNDERGRADUATE Materials Science & Engineering  

E-Print Network [OSTI]

UNDERGRADUATE HANDBOOK Materials Science & Engineering 2013 2014 #12;STUDYING FOR A MATERIALS SCIENCE AND ENGINEERING DEGREE Materials Science and Engineering inter-twines numerous disciplines that still gives the students the opportunity to study science while earning an engineering degree. Materials

Tipple, Brett

152

Materials Science & Engineering  

E-Print Network [OSTI]

Materials Science & Engineering The University of Utah 2014-15 Undergraduate Handbook #12;STUDYING FOR A MATERIALS SCIENCE AND ENGINEERING DEGREE Materials Science and Engineering inter-twines numerous disciplines that still gives the students the opportunity to study science while earning an engineering degree. Materials

Simons, Jack

153

A Materials Facilities Initiative -  

E-Print Network [OSTI]

A Materials Facilities Initiative - FMITS & MPEX D.L. Hillis and ORNL Team Fusion & Materials for Nuclear Systems Division July 10, 2014 #12;2 Materials Facilities Initiative JET ITER FNSF Fusion Reactor Challenges for materials: fluxes and fluence, temperatures 50 x divertor ion fluxes up to 100 x neutron

154

Computational Chemical Materials Engineering  

E-Print Network [OSTI]

: Thermal barrier coatings, wear resistance coatings, radiation resistant materials · Materials for opticalHome Computational Chemical and Materials Engineering Tahir Cagin Chemical Engineering Department to understand behavior and properties of materials as a function of ­ Chemical constitution ­ Composition

155

Microsoft Word - 2010 NNSS CEF Tour and Mtg. _August 24-25,...  

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

Currently, limited operations involving fissile material are authorized to perform subcritical measurements and associated activities pending startup authorization for performing...

156

CRAD, Packaging and Transfer of Hazardous Materials and Materials...  

Office of Environmental Management (EM)

CRAD, Packaging and Transfer of Hazardous Materials and Materials of National Security Interest Assessment Plan CRAD, Packaging and Transfer of Hazardous Materials and Materials of...

157

Supporting Online Material Materials and Methods  

E-Print Network [OSTI]

1 Supporting Online Material Materials and Methods (15) For all possible earthquake pairs. The parameters chosen for window length, filter bandpass, negative sidelobe identification, and cross-correlation threshold are appropriate for high-frequency earthquakes. In order to remove false positives or poor data

Wolfe, Cecily J.

158

SUPPORTING ONLINE MATERIAL Materials and Methods  

E-Print Network [OSTI]

SUPPORTING ONLINE MATERIAL Materials and Methods Two adult male rhesus monkeys (Macaca mulatta with a head-holding device (S1), scleral search coil for monitoring eye position (S2) and a recording chamber monkeys remain actively engaged in experiments, so precise histological identification of recording sites

Newsome, William

159

Puncture detecting barrier materials  

DOE Patents [OSTI]

A method and apparatus for continuous real-time monitoring of the integrity of protective barrier materials, particularly protective barriers against toxic, radioactive and biologically hazardous materials has been developed. Conductivity, resistivity or capacitance between conductive layers in the multilayer protective materials is measured by using leads connected to electrically conductive layers in the protective barrier material. The measured conductivity, resistivity or capacitance significantly changes upon a physical breach of the protective barrier material. 4 figs.

Hermes, R.E.; Ramsey, D.R.; Stampfer, J.F.; Macdonald, J.M.

1998-03-31T23:59:59.000Z

160

Joining of dissimilar materials  

DOE Patents [OSTI]

A method of joining dissimilar materials having different ductility, involves two principal steps: Decoration of the more ductile material's surface with particles of a less ductile material to produce a composite; and, sinter-bonding the composite produced to a joining member of a less ductile material. The joining method is suitable for joining dissimilar materials that are chemically inert towards each other (e.g., metal and ceramic), while resulting in a strong bond with a sharp interface between the two materials. The joining materials may differ greatly in form or particle size. The method is applicable to various types of materials including ceramic, metal, glass, glass-ceramic, polymer, cermet, semiconductor, etc., and the materials can be in various geometrical forms, such as powders, fibers, or bulk bodies (foil, wire, plate, etc.). Composites and devices with a decorated/sintered interface are also provided.

Tucker, Michael C; Lau, Grace Y; Jacobson, Craig P

2012-10-16T23:59:59.000Z

Note: This page contains sample records for the topic "weapons-usable fissile materials" 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

Demonstration (DEMO) of Radio Frequency Identification (RFID) system for tracking and monitoring of nuclear materials.  

SciTech Connect (OSTI)

The US Department of Energy (DOE) [Environmental Management (EM), Office of Packaging and Transportation (EM-45)] Packaging Certification Program (PCP) has developed a radiofrequency identification (RFID) tracking and monitoring system for the management of nuclear materials packages during storage and transportation. The system, developed by the PCP team at Argonne National Laboratory, involves hardware modification, application software development, secured database and web server development, and irradiation experiments. In April 2008, Argonne tested key features of the RFID tracking and monitoring system in a weeklong, 1700 mile (2736 km) demonstration employing 14 empty type B fissile material drums of three designs (models 9975, 9977 and ES-3100) that have been certified for shipment by the DOE and the US Nuclear Regulatory Commission. The demonstration successfully integrated global positioning system (GPS) technology for vehicle tracking, satellite/cellular (general packet radio service, or GPRS) technologies for wireless communication, and active RFID tags with multiple sensors (seal integrity, shock, temperature, humidity and battery status) on drums. In addition, the demonstration integrated geographic information system (GIS) technology with automatic alarm notifications of incidents and generated buffer zone reports for emergency response and management of staged incidents. The demonstration was sponsored by EM and the US National Nuclear Security Administration, with the participation of Argonne, Savannah River and Oak Ridge National Laboratories. Over 50 authorised stakeholders across the country observed the demonstration via secured Internet access. The DOE PCP and national laboratories are working on several RFID system implementation projects at selected DOE sites, as well as continuing device and systems development and widening applications beyond DOE sites and possibly beyond nuclear materials to include other radioactive materials.

Tsai, H. C.; Chen, K.; Liu, Y. Y.; Shuler, J. (Decision and Information Sciences); (USDOE)

2010-01-01T23:59:59.000Z

162

Materials for breeding blankets  

SciTech Connect (OSTI)

There are several candidate concepts for tritium breeding blankets that make use of a number of special materials. These materials can be classified as Primary Blanket Materials, which have the greatest influence in determining the overall design and performance, and Secondary Blanket Materials, which have key functions in the operation of the blanket but are less important in establishing the overall design and performance. The issues associated with the blanket materials are specified and several examples of materials performance are given. Critical data needs are identified.

Mattas, R.F.; Billone, M.C.

1995-09-01T23:59:59.000Z

163

CALMOS: Innovative device for the measurement of nuclear heating in material testing reactors  

SciTech Connect (OSTI)

An R and D program has been carried out since 2002 in order to improve gamma heating measurements in the 70 MWth OSIRIS Material Testing Reactor operated by CEA's Nuclear Energy Div. at the Saclay research center. Throughout this program an innovative calorimetric probe associated to a specific handling system has been designed in order to make measurements both along the fissile height and on the upper part of the core, where nuclear heating rates still remain high. Two mock-ups of the probe were manufactured and tested in 2005 and 2009 in ex-core area of OSIRIS reactor for the process validation, while a displacement system has been especially designed to move the probe axially. A final probe has been designed thanks to modeling results and to preliminary measurements obtained with mock-ups irradiated to a heating level of 2W/g, This paper gives an overview of the development, describes the calorimetric probe, and expected advantages such as the possibility to use complementary methods to get the nuclear heating measurement. Results obtained with mock-ups irradiated in ex-core area of the reactor are presented and discussed. (authors)

Carcreff, H. [Alternative Energies and Atomic Energy Commission CEA, Saclay Center, DEN/DANS/DRSN/SIREN, Gif Sur Yvette, 91191 (France)

2011-07-01T23:59:59.000Z

164

Nanocomposites as thermoelectric materials  

E-Print Network [OSTI]

Thermoelectric materials have attractive applications in electric power generation and solid-state cooling. The performance of a thermoelectric device depends on the dimensionless figure of merit (ZT) of the material, ...

Hao, Qing

2010-01-01T23:59:59.000Z

165

Factors of material consumption  

E-Print Network [OSTI]

Historic consumption trends for materials have been studied by many researchers, and, in order to identify the main drivers of consumption, special attention has been given to material intensity, which is the consumption ...

Silva Daz, Pamela Cristina

2012-01-01T23:59:59.000Z

166

Earth-Abundant Materials  

Broader source: Energy.gov [DOE]

DOE funds research into Earth-abundant materials for thin-film solar applications in response to the issue of materials scarcity surrounding other photovoltaic (PV) technologies. Below are a list...

167

Nanostructured composite reinforced material  

DOE Patents [OSTI]

A family of materials wherein nanostructures and/or nanotubes are incorporated into a multi-component material arrangement, such as a metallic or ceramic alloy or composite/aggregate, producing a new material or metallic/ceramic alloy. The new material has significantly increased strength, up to several thousands of times normal and perhaps substantially more, as well as significantly decreased weight. The new materials may be manufactured into a component where the nanostructure or nanostructure reinforcement is incorporated into the bulk and/or matrix material, or as a coating where the nanostructure or nanostructure reinforcement is incorporated into the coating or surface of a "normal" substrate material. The nanostructures are incorporated into the material structure either randomly or aligned, within grains, or along or across grain boundaries.

Seals, Roland D. (Oak Ridge, TN); Ripley, Edward B. (Knoxville, TN); Ludtka, Gerard M. (Oak Ridge, TN)

2012-07-31T23:59:59.000Z

168

Institute for Materials Science  

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

Institute for Material Science Who we are and what we do 2:23 Institute for Materials Science: Alexander V. Balatsky IMS is an interdisciplinary research and educational center...

169

Materials Science & Engineering  

E-Print Network [OSTI]

and Forensics team in the Polymers and Coatings Group, MST-7. He graduated from the University of Toledo, aerogels, carbon fiber composites, damaged materials, and low density materials examining defects

170

Geopolymer Sealing Materials  

Broader source: Energy.gov [DOE]

DOE Geothermal Peer Review 2010 - Presentation. Project objectives: Develop and characterize field-applicable geopolymer temporary sealing materials in the laboratory and to transfer this developed material technology to geothermal drilling service companies as collaborators for field validation tests.

171

Instructions and Materials  

Broader source: Energy.gov [DOE]

The following are 2012 Program Peer Review Meeting instructions, materials and resource links for presenters and reviewers.

172

Advanced neutron absorber materials  

DOE Patents [OSTI]

A neutron absorbing material and method utilizing rare earth elements such as gadolinium, europium and samarium to form metallic glasses and/or noble base nano/microcrystalline materials, the neutron absorbing material having a combination of superior neutron capture cross sections coupled with enhanced resistance to corrosion, oxidation and leaching.

Branagan, Daniel J. (Idaho Falls, ID); Smolik, Galen R. (Idaho Falls, ID)

2000-01-01T23:59:59.000Z

173

Magnetocaloric Materials Stinus Jeppesen  

E-Print Network [OSTI]

Magnetocaloric Materials Stinus Jeppesen Risø-PhD-43(EN) Risø National Laboratory for Sustainable Jeppesen Title: Magnetocaloric Materials Division: Fuel Cells and Solid State Chemistry Division Risø.D. degree at The University of Copenhagen Abstract: New and improved magnetocaloric materials are one

174

Radioactive Materials License Commitments  

E-Print Network [OSTI]

Radioactive Materials License Commitments for The University of Texas at Austin May 2009 July 2009 in the use of radioactive materials. In July 1963, the State of Texas granted The University of Texas at Austin a broad radioactive materials license for research, development and instruction. While this means

175

LIFE Materials: Fuel Cycle and Repository Volume 11  

SciTech Connect (OSTI)

The fusion-fission LIFE engine concept provides a path to a sustainable energy future based on safe, carbon-free nuclear power with minimal nuclear waste. The LIFE design ultimately offers many advantages over current and proposed nuclear energy technologies, and could well lead to a true worldwide nuclear energy renaissance. When compared with existing and other proposed future nuclear reactor designs, the LIFE engine exceeds alternatives in the most important measures of proliferation resistance and waste minimization. The engine needs no refueling during its lifetime. It requires no removal of fuel or fissile material generated in the LIFE engine. It leaves no weapons-attractive material at the end of life. Although there is certainly a need for additional work, all indications are that the 'back end' of the fuel cycle does not to raise any 'showstopper' issues for LIFE. Indeed, the LIFE concept has numerous benefits: (1) Per unit of electricity generated, LIFE engines would generate 20-30 times less waste (in terms of mass of heavy metal) requiring disposal in a HLW repository than does the current once-through fuel cycle. (2) Although there may be advanced fuel cycles that can compete with LIFE's low mass flow of heavy metal, all such systems require reprocessing, with attendant proliferation concerns; LIFE engines can do this without enrichment or reprocessing. Moreover, none of the advanced fuel cycles can match the low transuranic content of LIFE waste. (3) The specific thermal power of LIFE waste is initially higher than that of spent LWR fuel. Nevertheless, this higher thermal load can be managed using appropriate engineering features during an interim storage period, and could be accommodated in a Yucca-Mountain-like repository by appropriate 'staging' of the emplacement of waste packages during the operational period of the repository. The planned ventilation rates for Yucca Mountain would be sufficient for LIFE waste to meet the thermal constraints of the repository design. (4) A simple, but arguably conservative, estimate for the dose from a repository containing 63,000 MT of spent LIFE fuel would have similar performance to the currently planned Yucca Mountain Repository. This indicates that a properly designed 'LIFE Repository' would almost certainly meet the proposed Nuclear Regulatory Commission standards for dose to individuals, even though the waste in such a repository would have produced 20-30 times more generated electricity than the reference case for Yucca Mountain. The societal risk/benefit ratio for a LIFE repository would therefore be significantly better than for currently planned repositories for LWR fuel.

Shaw, H; Blink, J A

2008-12-12T23:59:59.000Z

176

Materials Science and Materials Chemistry for Large Scale Electrochemi...  

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

Science and Materials Chemistry for Large Scale Electrochemical Energy Storage: From Transportation to Electrical Grid Materials Science and Materials Chemistry for Large Scale...

177

Montani, Kohn, Smith and Schultz (2006), Supplemental Material Supplemental Material  

E-Print Network [OSTI]

Montani, Kohn, Smith and Schultz (2006), Supplemental Material 1 Supplemental Material A. Entropy, Kohn, Smith and Schultz (2006), Supplemental Material 2 occupied, it is ambiguous whether

Smith, Matthew A.

178

SMERDON ET AL.: AUXILIARY MATERIAL Auxiliary Material  

E-Print Network [OSTI]

run [Ammann et al., 2007; hereinafter CCSM] and the GKSS ECHO-g ERIK2 run [González-Rouco et al., 2006; hereinafter ECHO-g]. The annual means of the modeled temperature fields are interpolated to 5° latitude;SMERDON ET AL.: AUXILIARY MATERIAL 2 ECHO-g simulations, respectively. The above conventions

Smerdon, Jason E.

179

Portsmoulh/Paducah Project Office  

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

material DMSA U.S. Department of Energy Material Storage Area Fiss fissile ID identification LLW low-level waste PACM presumed asbestos-containing material PCB ...

180

Absolute nuclear material assay  

DOE Patents [OSTI]

A method of absolute nuclear material assay of an unknown source comprising counting neutrons from the unknown source and providing an absolute nuclear material assay utilizing a model to optimally compare to the measured count distributions. In one embodiment, the step of providing an absolute nuclear material assay comprises utilizing a random sampling of analytically computed fission chain distributions to generate a continuous time-evolving sequence of event-counts by spreading the fission chain distribution in time.

Prasad, Manoj K. (Pleasanton, CA); Snyderman, Neal J. (Berkeley, CA); Rowland, Mark S. (Alamo, CA)

2012-05-15T23:59:59.000Z

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


181

Composite of refractory material  

DOE Patents [OSTI]

A composite refractory material composition comprises a boron carbide matrix and minor constituents of yttrium-boron-oxygen-carbon phases uniformly distributed throughout the boron carbide matrix.

Holcombe, C.E.; Morrow, M.S.

1994-07-19T23:59:59.000Z

182

Radiation Safety Training Materials  

Broader source: Energy.gov [DOE]

The following Handbooks and Standard provide recommended hazard specific training material for radiological workers at DOE facilities and for various activities.

183

Materials Research Staff  

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

generation and detection, this approach naturally lends itself to in situ monitoring of material property evolution. The temporal laser pulse length and the corresponding...

184

Webinar: Materials Genome Initative  

Broader source: Energy.gov [DOE]

Audio recording and text version of the Fuel Cell Technologies Office webinar titled "Materials Genome Initiative," originally presented on December 2, 2014.

185

Composite of refractory material  

DOE Patents [OSTI]

A composite refractory material composition comprises a boron carbide matrix and minor constituents of yttrium-boron-oxygen-carbon phases uniformly distributed throughout the boron carbide matrix.

Holcombe, Cressie E. (Knoxville, TN); Morrow, Marvin S. (Kingston, TN)

1994-01-01T23:59:59.000Z

186

Geopolymer Sealing Materials  

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

Geopolymer Sealing Materials PI : Dr. Tomas Butcher Presenter: Dr. Toshi Sugama Brookhaven National Laboratory May 18, 2010 This presentation does not contain any proprietary...

187

Materials for MA 182.  

E-Print Network [OSTI]

Materials for MA 182. INSTRUCTOR: Richard Penney. Office: MATH 822: Telephone: 494-1968: e-mail: rcp@math.purdue.edu: Office Hours: Mon, Tu, Fri,

188

Layered Cathode Materials  

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

Layered Cathode Materials presented by Michael Thackeray Chemical Sciences and Engineering Division, Argonne Annual Merit Review DOE Vehicle Technologies Program Washington, D.C....

189

EMSL - battery materials  

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

battery-materials en Modeling Interfacial Glass-Water Reactions: Recent Advances and Current Limitations. http:www.emsl.pnl.govemslwebpublicationsmodeling-interfacial-glass-wa...

190

Thermoelectric materials having porosity  

DOE Patents [OSTI]

A thermoelectric material and a method of making a thermoelectric material are provided. In certain embodiments, the thermoelectric material comprises at least 10 volume percent porosity. In some embodiments, the thermoelectric material has a zT greater than about 1.2 at a temperature of about 375 K. In some embodiments, the thermoelectric material comprises a topological thermoelectric material. In some embodiments, the thermoelectric material comprises a general composition of (Bi.sub.1-xSb.sub.x).sub.u(Te.sub.1-ySe.sub.y).sub.w, wherein 0.ltoreq.x.ltoreq.1, 0.ltoreq.y.ltoreq.1, 1.8.ltoreq.u.ltoreq.2.2, 2.8.ltoreq.w.ltoreq.3.2. In further embodiments, the thermoelectric material includes a compound having at least one group IV element and at least one group VI element. In certain embodiments, the method includes providing a powder comprising a thermoelectric composition, pressing the powder, and sintering the powder to form the thermoelectric material.

Heremans, Joseph P.; Jaworski, Christopher M.; Jovovic, Vladimir; Harris, Fred

2014-08-05T23:59:59.000Z

191

Management of Nuclear Materials  

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

To establish requirements for the lifecycle management of DOE owned and/or managed accountable nuclear materials. Cancels DOE O 5660.1B.

2009-08-17T23:59:59.000Z

192

Radioactive Material Transportation Practices  

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

Establishes standard transportation practices for Departmental programs to use in planning and executing offsite shipments of radioactive materials including radioactive waste. Does not cancel other directives.

2002-09-23T23:59:59.000Z

193

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...

194

Vibrational Damping of Composite Materials  

E-Print Network [OSTI]

Smart Structures and Materials, 3989:531- 538. Biggerstaff,2002. Electroviscoelastic Materials As Active Dampers,Smart Structures and Materials, 4695:345-350. Biggerstaff,

Biggerstaff, Janet M.

2006-01-01T23:59:59.000Z

195

Deformation Mechanisms in Nanocrystalline Materials  

E-Print Network [OSTI]

2010 METALLURGICAL AND MATERIALS TRANSACTIONS A 47. F.A.12. METALLURGICAL AND MATERIALS TRANSACTIONS A VOLUME 41A,of Slip: Progress in Materials Science, Pergamon Press,

Mohamed, Farghalli A.; Yang, Heather

2010-01-01T23:59:59.000Z

196

Advanced Materials | More Science | ORNL  

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

Advanced Materials SHARE Advanced Materials ORNL has the nation's most comprehensive materials research program and is a world leader in research that supports the development of...

197

MULTISCALE PHENOMENA IN MATERIALS  

SciTech Connect (OSTI)

This project developed and supported a technology base in nonequilibrium phenomena underpinning fundamental issues in condensed matter and materials science, and applied this technology to selected problems. In this way the increasingly sophisticated synthesis and characterization available for classes of complex electronic and structural materials provided a testbed for nonlinear science, while nonlinear and nonequilibrium techniques helped advance our understanding of the scientific principles underlying the control of material microstructure, their evolution, fundamental to macroscopic functionalities. The project focused on overlapping areas of emerging thrusts and programs in the Los Alamos materials community for which nonlinear and nonequilibrium approaches will have decisive roles and where productive teamwork among elements of modeling, simulations, synthesis, characterization and applications could be anticipated--particularly multiscale and nonequilibrium phenomena, and complex matter in and between fields of soft, hard and biomimetic materials. Principal topics were: (i) Complex organic and inorganic electronic materials, including hard, soft and biomimetic materials, self-assembly processes and photophysics; (ii) Microstructure and evolution in multiscale and hierarchical materials, including dynamic fracture and friction, dislocation and large-scale deformation, metastability, and inhomogeneity; and (iii) Equilibrium and nonequilibrium phases and phase transformations, emphasizing competing interactions, frustration, landscapes, glassy and stochastic dynamics, and energy focusing.

A. BISHOP

2000-09-01T23:59:59.000Z

198

Impacted material placement plans  

SciTech Connect (OSTI)

Impacted material placement plans (IMPP) are documents identifying the essential elements in placing remediation wastes into disposal facilities. Remediation wastes or impacted material(s) are those components used in the construction of the disposal facility exclusive of the liners and caps. The components might include soils, concrete, rubble, debris, and other regulatory approved materials. The IMPP provides the details necessary for interested parties to understand the management and construction practices at the disposal facility. The IMPP should identify the regulatory requirements from applicable DOE Orders, the ROD(s) (where a part of a CERCLA remedy), closure plans, or any other relevant agreements or regulations. Also, how the impacted material will be tracked should be described. Finally, detailed descriptions of what will be placed and how it will be placed should be included. The placement of impacted material into approved on-site disposal facilities (OSDF) is an integral part of gaining regulatory approval. To obtain this approval, a detailed plan (Impacted Material Placement Plan [IMPP]) was developed for the Fernald OSDF. The IMPP provides detailed information for the DOE, site generators, the stakeholders, regulatory community, and the construction subcontractor placing various types of impacted material within the disposal facility.

Hickey, M.J.

1997-01-29T23:59:59.000Z

199

Nanocrystalline heterojunction materials  

DOE Patents [OSTI]

Mesoporous nanocrystalline titanium dioxide heterojunction materials are disclosed. In one disclosed embodiment, materials comprising a core of titanium dioxide and a shell of a molybdenum oxide exhibit a decrease in their photoadsorption energy as the size of the titanium dioxide core decreases.

Elder, Scott H.; Su, Yali; Gao, Yufei; Heald, Steve M.

2003-07-15T23:59:59.000Z

200

Materials for Information Technology  

E-Print Network [OSTI]

on thin-film and nano-scale materials. The papers include content ranging from materials-related aspects for these fascinating and useful mate- rials. /jr Adv. Eng. Mater. 2009, 11, Issue 4 Colloidal Hollow Spheres Colloidal hollow spheres of conduct- ing polymers such as polypyrrole (PPy) or polyaniline (PAni) are produced

Tang, Ben Zhong

Note: This page contains sample records for the topic "weapons-usable fissile materials" 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

Nanocrystalline Heterojunction Materials  

DOE Patents [OSTI]

Mesoporous nanocrystalline titanium dioxide heterojunction materials and methods of making the same are disclosed. In one disclosed embodiment, materials comprising a core of titanium dioxide and a shell of a molybdenum oxide exhibit a decrease in their photoadsorption energy as the size of the titanium dioxide core decreases.

Elder, Scott H. (Portland, OR); Su, Yali (Richland, WA); Gao, Yufei (Blue Bell, PA); Heald, Steve M. (Downers Grove, IL)

2004-02-03T23:59:59.000Z

202

Materials Science and Technology Mechanical and Materials Engineering  

E-Print Network [OSTI]

Materials Science and Technology Metallurgy Mechanical and Materials Engineering Materials Science with Energy Engineering Materials Science with Business Management Course Prospectus School of Metallurgy for Metallurgy and Materials What difference will you make? #12;2 School of Metallurgy and Materials Contents

Birmingham, University of

203

ALPHA SPECTROMETRIC EVALUATION OF SRM-995 AS A POTENTIAL URANIUM/THORIUM DOUBLE TRACER SYSTEM FOR AGE-DATING URANIUM MATERIALS  

SciTech Connect (OSTI)

Uranium-233 (t{sub 1/2} {approx} 1.59E5 years) is an artificial, fissile isotope of uranium that has significant importance in nuclear forensics. The isotope provides a unique signature in determining the origin and provenance of uranium-bearing materials and is valuable as a mass spectrometric tracer. Alpha spectrometry was employed in the critical evaluation of a {sup 233}U standard reference material (SRM-995) as a dual tracer system based on the in-growth of {sup 229}Th (t{sub 1/2} {approx} 7.34E3 years) for {approx}35 years following radiochemical purification. Preliminary investigations focused on the isotopic analysis of standards and unmodified fractions of SRM-995; all samples were separated and purified using a multi-column anion-exchange scheme. The {sup 229}Th/{sup 233}U atom ratio for SRM-995 was found to be 1.598E-4 ({+-} 4.50%) using recovery-corrected radiochemical methods. Using the Bateman equations and relevant half-lives, this ratio reflects a material that was purified {approx} 36.8 years prior to this analysis. The calculated age is discussed in contrast with both the date of certification and the recorded date of last purification.

Beals, D.

2011-12-06T23:59:59.000Z

204

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

205

Degrees in Metallurgy and Materials  

E-Print Network [OSTI]

Degrees in Metallurgy and Materials Course outline School of Metallurgy and Materials Materials us? Dr Alessandro Mottura Undergraduate Admissions Tutor for Metallurgy and Materials What difference will you make? #12;Degrees in Metallurgy and Materials Understanding the properties of new materials

Birmingham, University of

206

Electrically conductive composite material  

DOE Patents [OSTI]

An electrically conductive composite material is disclosed which comprises a conductive open-celled, low density, microcellular carbon foam filled with a non-conductive polymer or resin. The composite material is prepared in a two-step process consisting of first preparing the microcellular carbon foam from a carbonizable polymer or copolymer using a phase separation process, then filling the carbon foam with the desired non-conductive polymer or resin. The electrically conductive composites of the present invention has a uniform and consistent pattern of filler distribution, and as a result is superior over prior art materials when used in battery components, electrodes, and the like. 2 figs.

Clough, R.L.; Sylwester, A.P.

1989-05-23T23:59:59.000Z

207

Electrically conductive composite material  

DOE Patents [OSTI]

An electrically conductive composite material is disclosed which comprises a conductive open-celled, low density, microcellular carbon foam filled with a non-conductive polymer or resin. The composite material is prepared in a two-step process consisting of first preparing the microcellular carbon foam from a carbonizable polymer or copolymer using a phase separation process, then filling the carbon foam with the desired non-conductive polymer or resin. The electrically conductive composites of the present invention has a uniform and consistent pattern of filler distribution, and as a result is superior over prior art materials when used in battery components, electrodes, and the like. 2 figs.

Clough, R.L.; Sylwester, A.P.

1988-06-20T23:59:59.000Z

208

Electrically conductive composite material  

DOE Patents [OSTI]

An electrically conductive composite material is disclosed which comprises a conductive open-celled, low density, microcellular carbon foam filled with a non-conductive polymer or resin. The composite material is prepared in a two-step process consisting of first preparing the microcellular carbon foam from a carbonizable polymer or copolymer using a phase separation process, then filling the carbon foam with the desired non-conductive polymer or resin. The electrically conductive composites of the present invention has a uniform and consistant pattern of filler distribution, and as a result is superior over prior art materials when used in battery components, electrodes, and the like.

Clough, Roger L. (Albuquerque, NM); Sylwester, Alan P. (Albuquerque, NM)

1989-01-01T23:59:59.000Z

209

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

210

ATS materials/manufacturing  

SciTech Connect (OSTI)

The Materials/Manufacturing Technology subelement is a part of the base technology portion of the Advanced Turbine Systems (ATS) Program. The work in this subelement is being performed predominantly by industry with assistance from national laboratories and universities. The projects in this subelement are aimed toward hastening the incorporation of new materials and components in gas turbines. Work is currently ongoing on thermal barrier coatings (TBCs), the scale-up of single crystal airfoil manufacturing technologies, materials characterization, and technology information exchange. This paper presents highlights of the activities during the past year. 12 refs., 24 figs., 4 tabs.

Karnitz, M.A.; Wright, I.G.; Ferber, M.K. [and others

1997-11-01T23:59:59.000Z

211

Materials at LANL  

SciTech Connect (OSTI)

Exploring the physics, chemistry, and metallurgy of materials has been a primary focus of Los Alamos National Laboratory since its inception. In the early 1940s, very little was known or understood about plutonium, uranium, or their alloys. In addition, several new ionic, polymeric, and energetic materials with unique properties were needed in the development of nuclear weapons. As the Laboratory has evolved, and as missions in threat reduction, defense, energy, and meeting other emerging national challenges have been added, the role of materials science has expanded with the need for continued improvement in our understanding of the structure and properties of materials and in our ability to synthesize and process materials with unique characteristics. Materials science and engineering continues to be central to this Laboratory's success, and the materials capability truly spans the entire laboratory - touching upon numerous divisions and directorates and estimated to include >1/3 of the lab's technical staff. In 2006, Los Alamos and LANS LLC began to redefine our future, building upon the laboratory's established strengths and promoted by strongly interdependent science, technology and engineering capabilities. Eight Grand Challenges for Science were set forth as a technical framework for bridging across capabilities. Two of these grand challenges, Fundamental Understanding of Materials and Superconductivity and Actinide Science. were clearly materials-centric and were led out of our organizations. The complexity of these scientific thrusts was fleshed out through workshops involving cross-disciplinary teams. These teams refined the grand challenge concepts into actionable descriptions to be used as guidance for decisions like our LDRD strategic investment strategies and as the organizing basis for our external review process. In 2008, the Laboratory published 'Building the Future of Los Alamos. The Premier National Security Science Laboratory,' LA-UR-08-1541. This document introduced three strategic thrusts that crosscut the Grand Challenges and define future laboratory directions and facilities: (1) Information Science and Technology enabl ing integrative and predictive science; (2) Experimental science focused on materials for the future; and (3) Fundamental forensic science for nuclear, biological, and chemical threats. The next step for the Materials Capability was to develop a strategic plan for the second thrust, Materials for the Future. within the context of a capabilities-based Laboratory. This work has involved extending our 2006-2007 Grand Challenge workshops, integrating materials fundamental challenges into the MaRIE definition, and capitalizing on the emerging materials-centric national security missions. Strategic planning workshops with broad leadership and staff participation continued to hone our scientific directions and reinforce our strength through interdependence. By the Fall of 2008, these workshops promoted our primary strength as the delivery of Predictive Performance in applications where Extreme Environments dominate and where the discovery of Emergent Phenomena is a critical. These planning efforts were put into action through the development of our FY10 LDRD Strategic Investment Plan where the Materials Category was defined to incorporate three central thrusts: Prediction and Control of Performance, Extreme Environments and Emergent Phenomena. As with all strategic planning, much of the benefit is in the dialogue and cross-fertilization of ideas that occurs during the process. By winter of 2008/09, there was much agreement on the evolving focus for the Materials Strategy, but there was some lingering doubt over Prediction and Control of Performance as one of the three central thrusts, because it overarches all we do and is, truly, the end goal for materials science and engineering. Therefore, we elevated this thrust within the overarching vision/mission and introduce the concept of Defects and Interfaces as a central thrust that had previously been implied but not clearly articulated.

Taylor, Antoinette J [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

212

Materials Science & Engineering  

E-Print Network [OSTI]

. Aucierllo has edited 19 books, published about 450 articles, holds 14 patents, and has organized, chaired and nanocarbon thin films are providing the bases for new physics, new materials science and chemistry

213

Microdrilling of Biocompatible Materials  

E-Print Network [OSTI]

This research studies microdrilling of biocompatible materials including commercially pure titanium, 316L stainless steel, polyether ether ketone (PEEK) and aluminum 6061-T6. A microdrilling technique that uses progressive pecking and micromist...

Mohanty, Sankalp

2012-02-14T23:59:59.000Z

214

Nuclear Material Packaging Manual  

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

The manual provides detailed packaging requirements for protecting workers from exposure to nuclear materials stored outside of an approved engineered contamination barrier. No cancellation. Certified 11-18-10.

2008-03-07T23:59:59.000Z

215

Mesoporous carbon materials  

DOE Patents [OSTI]

The invention is directed to a method for fabricating a mesoporous carbon material, the method comprising subjecting a precursor composition to a curing step followed by a carbonization step, the precursor composition comprising: (i) a templating component comprised of a block copolymer, (ii) a phenolic compound or material, (iii) a crosslinkable aldehyde component, and (iv) at least 0.5 M concentration of a strong acid having a pKa of or less than -2, wherein said carbonization step comprises heating the precursor composition at a carbonizing temperature for sufficient time to convert the precursor composition to a mesoporous carbon material. The invention is also directed to a mesoporous carbon material having an improved thermal stability, preferably produced according to the above method.

Dai, Sheng; Wang, Xiqing

2013-08-20T23:59:59.000Z

216

Critical Materials Workshop  

Broader source: Energy.gov [DOE]

AMO hosted a public workshop on Tuesday, April 3, 2012 in Arlington, VA to provide background information on critical materials assessment, the current research within DOE related to critical...

217

Management of Nuclear Materials  

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

To establish requirements and procedures for the management of nuclear materials within the Department of Energy (DOE). Cancels DOE 5660.1A. Canceled by DOE O 410.2.

1994-05-26T23:59:59.000Z

218

CRITICAL MATERIALS INSTITUTE PROJECTS  

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

INL Recovery of Critical Materials from Consumer Devices 3 3-2 3.2.6 McCall, Scott LLNL Additive Manufacturing of Permanent Magnets 2 2-1 2.1.2 McGuire, Michael ORNL...

219

CRITICAL MATERIALS INSTITUTE PROJECTS  

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

INL National Technology Roadmap for Critical Materials 4 4-3 4.3.3 McCall, Scott LLNL Additive Manufacturing of Permanent Magnets 2 2-1 2.1.2 Payne, Steve LLNL New Efficient...

220

MATERIALS SCIENCE HEALTHCARE POLICY  

E-Print Network [OSTI]

for Polymer Research are paving the way to optimizing organic substances for use in solar cells, light-emitting diodes and memory chips, and are using molecular materials to develop electronic components

Falge, Eva

Note: This page contains sample records for the topic "weapons-usable fissile materials" 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

Electrically conductive material  

DOE Patents [OSTI]

An electrically conductive material for use in solid oxide fuel cells, electrochemical sensors for combustion exhaust, and various other applications possesses increased fracture toughness over available materials, while affording the same electrical conductivity. One embodiment of the sintered electrically conductive material consists essentially of cubic ZrO.sub.2 as a matrix and 6-19 wt. % monoclinic ZrO.sub.2 formed from particles having an average size equal to or greater than about 0.23 microns. Another embodiment of the electrically conductive material consists essentially at cubic ZrO.sub.2 as a matrix and 10-30 wt. % partially stabilized zirconia (PSZ) formed from particles having an average size of approximately 3 microns.

Singh, Jitendra P. (Bollingbrook, IL); Bosak, Andrea L. (Burnam, IL); McPheeters, Charles C. (Woodridge, IL); Dees, Dennis W. (Woodridge, IL)

1993-01-01T23:59:59.000Z

222

Electrically conductive material  

DOE Patents [OSTI]

An electrically conductive material is described for use in solid oxide fuel cells, electrochemical sensors for combustion exhaust, and various other applications possesses increased fracture toughness over available materials, while affording the same electrical conductivity. One embodiment of the sintered electrically conductive material consists essentially of cubic ZrO[sub 2] as a matrix and 6-19 wt. % monoclinic ZrO[sub 2] formed from particles having an average size equal to or greater than about 0.23 microns. Another embodiment of the electrically conductive material consists essentially at cubic ZrO[sub 2] as a matrix and 10-30 wt. % partially stabilized zirconia (PSZ) formed from particles having an average size of approximately 3 microns. 8 figures.

Singh, J.P.; Bosak, A.L.; McPheeters, C.C.; Dees, D.W.

1993-09-07T23:59:59.000Z

223

Management of Nuclear Materials  

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

To establish requirements for the lifecycle management of DOE owned and/or managed accountable nuclear materials. Cancels DOE O 410.2. Admin Chg 1 dated 4-10-2014, cancels DOE O 410.2.

2009-08-17T23:59:59.000Z

224

Nuclear material operations manual  

SciTech Connect (OSTI)

This manual provides a concise and comprehensive documentation of the operating procedures currently practiced at Sandia National Laboratories with regard to the management, control, and accountability of nuclear materials. The manual is divided into chapters which are devoted to the separate functions performed in nuclear material operations-management, control, accountability, and safeguards, and the final two chapters comprise a document which is also issued separately to provide a summary of the information and operating procedures relevant to custodians and users of radioactive and nuclear materials. The manual also contains samples of the forms utilized in carrying out nuclear material activities. To enhance the clarity of presentation, operating procedures are presented in the form of playscripts in which the responsible organizations and necessary actions are clearly delineated in a chronological fashion from the initiation of a transaction to its completion.

Tyler, R.P.

1981-02-01T23:59:59.000Z

225

Reversible hydrogen storage materials  

DOE Patents [OSTI]

In accordance with the present disclosure, a process for synthesis of a complex hydride material for hydrogen storage is provided. The process includes mixing a borohydride with at least one additive agent and at least one catalyst and heating the mixture at a temperature of less than about 600.degree. C. and a pressure of H.sub.2 gas to form a complex hydride material. The complex hydride material comprises MAl.sub.xB.sub.yH.sub.z, wherein M is an alkali metal or group IIA metal, Al is the element aluminum, x is any number from 0 to 1, B is the element boron, y is a number from 0 to 13, and z is a number from 4 to 57 with the additive agent and catalyst still being present. The complex hydride material is capable of cyclic dehydrogenation and rehydrogenation and has a hydrogen capacity of at least about 4 weight percent.

Ritter, James A. (Lexington, SC); Wang, Tao (Columbia, SC); Ebner, Armin D. (Lexington, SC); Holland, Charles E. (Cayce, SC)

2012-04-10T23:59:59.000Z

226

Mesoporous carbon materials  

DOE Patents [OSTI]

The invention is directed to a method for fabricating a mesoporous carbon material, the method comprising subjecting a precursor composition to a curing step followed by a carbonization step, the precursor composition comprising: (i) a templating component comprised of a block copolymer, (ii) a phenolic compound or material, (iii) a crosslinkable aldehyde component, and (iv) at least 0.5 M concentration of a strong acid having a pKa of or less than -2, wherein said carbonization step comprises heating the precursor composition at a carbonizing temperature for sufficient time to convert the precursor composition to a mesoporous carbon material. The invention is also directed to a mesoporous carbon material having an improved thermal stability, preferably produced according to the above method.

Dai, Sheng (Knoxville, TN); Wang, Xiqing (Oak Ridge, TN)

2012-02-14T23:59:59.000Z

227

Nano-composite materials  

DOE Patents [OSTI]

Nano-composite materials are disclosed. An exemplary method of producing a nano-composite material may comprise co-sputtering a transition metal and a refractory metal in a reactive atmosphere. The method may also comprise co-depositing a transition metal and a refractory metal composite structure on a substrate. The method may further comprise thermally annealing the deposited transition metal and refractory metal composite structure in a reactive atmosphere.

Lee, Se-Hee; Tracy, C. Edwin; Pitts, J. Roland

2010-05-25T23:59:59.000Z

228

Piston actuated nastic materials  

E-Print Network [OSTI]

PISTON ACTUATED NASTIC MATERIALS A Thesis by VIRAL SHAH Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE December 2008... Major Subject: Mechanical Engineering PISTON ACTUATED NASTIC MATERIALS A Thesis by VIRAL SHAH Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER...

Shah, Viral

2009-05-15T23:59:59.000Z

229

Biomimetic hydrogel materials  

DOE Patents [OSTI]

Novel biomimetic hydrogel materials and methods for their preparation. Hydrogels containing acrylamide-functionalized carbohydrate, sulfoxide, sulfide or sulfone copolymerized with a hydrophilic or hydrophobic copolymerizing material selected from the group consisting of an acrylamide, methacrylamide, acrylate, methacrylate, vinyl and a derivative thereof present in concentration from about 1 to about 99 wt %. and methods for their preparation. The method of use of the new hydrogels for fabrication of soft contact lenses and biomedical implants.

Bertozzi, Carolyn (Albany, CA); Mukkamala, Ravindranath (Houston, TX); Chen, Qing (Albany, CA); Hu, Hopin (Albuquerque, NM); Baude, Dominique (Creteil, FR)

2000-01-01T23:59:59.000Z

230

Biomimetic Hydrogel Materials  

DOE Patents [OSTI]

Novel biomimetic hydrogel materials and methods for their preparation. Hydrogels containing acrylamide-functionalized carbohydrate, sulfoxide, sulfide or sulfone copolymerized with a hydrophilic or hydrophobic copolymerizing material selected from the group consisting of an acrylamide, methacrylamide, acrylate, methacrylate, vinyl and a derivative thereof present in concentration from about 1 to about 99 wt %. and methods for their preparation. The method of use of the new hydrogels for fabrication of soft contact lenses and biomedical implants.

Bertozzi, Carolyn (Albany, CA), Mukkamala, Ravindranath (Houston, TX), Chen, Oing (Albany, CA), Hu, Hopin (Albuquerque, NM), Baude, Dominique (Creteil, FR)

2003-04-22T23:59:59.000Z

231

Nanostructured Materials for Energy Generation and Storage  

E-Print Network [OSTI]

xi Material CharacterizationThermoelectric Materials . . . . . . . . Graphene-Like5 Nanostructured Materials for Electrochemical Energy

Khan, Javed Miller

2012-01-01T23:59:59.000Z

232

Fabrication of Tungsten-Rhenium Cladding materials via Spark Plasma Sintering for Ultra High Temperature Reactor Applications  

SciTech Connect (OSTI)

This research will develop an optimized, cost-effective method for producing high-purity tungsten-rhenium alloyed fuel clad forms that are crucial for the development of a very high-temperature nuclear reactor. The study will provide critical insight into the fundamental behavior (processing-microstructure- property correlations) of W-Re alloys made using this new fabrication process comprising high-energy ball milling (HEBM) and spark plasma sintering (SPS). A broader goal is to re-establish the U.S. lead in the research field of refractory alloys, such as W-Re systems, with potential applications in very high-temperature nuclear reactors. An essential long-term goal for nuclear power is to develop the capability of operating nuclear reactors at temperatures in excess of 1,000K. This capability has applications in space exploration and some special terrestrial uses where high temperatures are needed in certain chemical or reforming processes. Refractory alloys have been identified as being capable of withstanding temperatures in excess of 1,000K and are considered critical for the development of ultra hightemperature reactors. Tungsten alloys are known to possess extraordinary properties, such as excellent high-temperature capability, including the ability to resist leakage of fissile materials when used as a fuel clad. However, there are difficulties with the development of refractory alloys: 1) lack of basic experimental data on thermodynamics and mechanical and physical properties, and 2) challenges associated with processing these alloys.

Charit, Indrajit; Butt, Darryl; Frary, Megan; Carroll, Mark

2012-11-05T23:59:59.000Z

233

Microwave impregnation of porous materials with thermal energy storage materials  

DOE Patents [OSTI]

A method for impregnating a porous, non-metallic construction material with a solid phase-change material is described. The phase-change material in finely divided form is spread onto the surface of the porous material, after which the porous material is exposed to microwave energy for a time sufficient to melt the phase-change material. The melted material is spontaneously absorbed into the pores of the porous material. A sealing chemical may also be included with the phase-change material (or applied subsequent to the phase-change material) to seal the surface of the porous material. Fire retardant chemicals may also be included with the phase-change materials. The treated construction materials are better able to absorb thermal energy and exhibit increased heat storage capacity.

Benson, David K. (Golden, CO); Burrows, Richard W. (Conifer, CO)

1993-01-01T23:59:59.000Z

234

Microwave impregnation of porous materials with thermal energy storage materials  

DOE Patents [OSTI]

A method for impregnating a porous, non-metallic construction material with a solid phase-change material is described. The phase-change material in finely divided form is spread onto the surface of the porous material, after which the porous material is exposed to microwave energy for a time sufficient to melt the phase-change material. The melted material is spontaneously absorbed into the pores of the porous material. A sealing chemical may also be included with the phase-change material (or applied subsequent to the phase-change material) to seal the surface of the porous material. Fire retardant chemicals may also be included with the phase-change materials. The treated construction materials are better able to absorb thermal energy and exhibit increased heat storage capacity.

Benson, D.K.; Burrows, R.W.

1993-04-13T23:59:59.000Z

235

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

236

Porous material neutron detector  

DOE Patents [OSTI]

A neutron detector employs a porous material layer including pores between nanoparticles. The composition of the nanoparticles is selected to cause emission of electrons upon detection of a neutron. The nanoparticles have a maximum dimension that is in the range from 0.1 micron to 1 millimeter, and can be sintered with pores thereamongst. A passing radiation generates electrons at one or more nanoparticles, some of which are scattered into a pore and directed toward a direction opposite to the applied electrical field. These electrons travel through the pore and collide with additional nanoparticles, which generate more electrons. The electrons are amplified in a cascade reaction that occurs along the pores behind the initial detection point. An electron amplification device may be placed behind the porous material layer to further amplify the electrons exiting the porous material layer.

Diawara, Yacouba (Oak Ridge, TN); Kocsis, Menyhert (Venon, FR)

2012-04-10T23:59:59.000Z

237

Oxygen ion conducting materials  

DOE Patents [OSTI]

An oxygen ion conducting ceramic oxide that has applications in industry including fuel cells, oxygen pumps, oxygen sensors, and separation membranes. The material is based on the idea that substituting a dopant into the host perovskite lattice of (La,Sr)MnO.sub.3 that prefers a coordination number lower than 6 will induce oxygen ion vacancies to form in the lattice. Because the oxygen ion conductivity of (La,Sr)MnO.sub.3 is low over a very large temperature range, the material exhibits a high overpotential when used. The inclusion of oxygen vacancies into the lattice by doping the material has been found to maintain the desirable properties of (La,Sr)MnO.sub.3, while significantly decreasing the experimentally observed overpotential.

Vaughey, John; Krumpelt, Michael; Wang, Xiaoping; Carter, J. David

2005-07-12T23:59:59.000Z

238

Oxygen ion conducting materials  

DOE Patents [OSTI]

An oxygen ion conducting ceramic oxide that has applications in industry including fuel cells, oxygen pumps, oxygen sensors, and separation membranes. The material is based on the idea that substituting a dopant into the host perovskite lattice of (La,Sr)MnO.sub.3 that prefers a coordination number lower than 6 will induce oxygen ion vacancies to form in the lattice. Because the oxygen ion conductivity of (La,Sr)MnO.sub.3 is low over a very large temperature range, the material exhibits a high overpotential when used. The inclusion of oxygen vacancies into the lattice by doping the material has been found to maintain the desirable properties of (La,Sr)MnO.sub.3, while significantly decreasing the experimentally observed overpotential.

Carter, J. David; Wang, Xiaoping; Vaughey, John; Krumpelt, Michael

2004-11-23T23:59:59.000Z

239

Apparatus for dispensing material  

DOE Patents [OSTI]

An apparatus capable of dispensing drops of material with volumes on the order of zeptoliters is described. In some embodiments of the inventive pipette the size of the droplets so dispensed is determined by the size of a hole, or channel, through a carbon shell encapsulating a reservoir that contains material to be dispensed. The channel may be formed by irradiation with an electron beam or other high-energy beam capable of focusing to a spot size less than about 5 nanometers. In some embodiments, the dispensed droplet remains attached to the pipette by a small thread of material, an atomic scale meniscus, forming a virtually free-standing droplet. In some embodiments the droplet may wet the pipette tip and take on attributes of supported drops. Methods for fabricating and using the pipette are also described.

Sutter, Peter Werner (Beach, NY); Sutter, Eli Anguelova (Beach, NY)

2011-07-05T23:59:59.000Z

240

Oxygen ion conducting materials  

DOE Patents [OSTI]

An oxygen ion conducting ceramic oxide that has applications in industry including fuel cells, oxygen pumps, oxygen sensors, and separation membranes. The material is based on the idea that substituting a dopant into the host perovskite lattice of (La,Sr)MnO.sub.3 that prefers a coordination number lower than 6 will induce oxygen ion vacancies to form in the lattice. Because the oxygen ion conductivity of (La,Sr)MnO.sub.3 is low over a very large temperature range, the material exhibits a high overpotential when used. The inclusion of oxygen vacancies into the lattice by doping the material has been found to maintain the desirable properties of (La,Sr)MnO.sub.3, while significantly decreasing the experimentally observed overpotential.

Vaughey, John (Elmhurst, IL); Krumpelt, Michael (Naperville, IL); Wang, Xiaoping (Downers Grove, IL); Carter, J. David (Bolingbrook, IL)

2003-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "weapons-usable fissile materials" 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

Optimized nanoporous materials.  

SciTech Connect (OSTI)

Nanoporous materials have maximum practical surface areas for electrical charge storage; every point in an electrode is within a few atoms of an interface at which charge can be stored. Metal-electrolyte interfaces make best use of surface area in porous materials. However, ion transport through long, narrow pores is slow. We seek to understand and optimize the tradeoff between capacity and transport. Modeling and measurements of nanoporous gold electrodes has allowed us to determine design principles, including the fact that these materials can deplete salt from the electrolyte, increasing resistance. We have developed fabrication techniques to demonstrate architectures inspired by these principles that may overcome identified obstacles. A key concept is that electrodes should be as close together as possible; this is likely to involve an interpenetrating pore structure. However, this may prove extremely challenging to fabricate at the finest scales; a hierarchically porous structure can be a worthy compromise.

Braun, Paul V. (University of Illinois at Urbana-Champaign, Urbana, IL); Langham, Mary Elizabeth; Jacobs, Benjamin W.; Ong, Markus D.; Narayan, Roger J. (North Carolina State University, Raleigh, NC); Pierson, Bonnie E. (North Carolina State University, Raleigh, NC); Gittard, Shaun D. (North Carolina State University, Raleigh, NC); Robinson, David B.; Ham, Sung-Kyoung (Korea Basic Science Institute, Gangneung, South Korea); Chae, Weon-Sik (Korea Basic Science Institute, Gangneung, South Korea); Gough, Dara V. (University of Illinois at Urbana-Champaign, Urbana, IL); Wu, Chung-An Max; Ha, Cindy M.; Tran, Kim L.

2009-09-01T23:59:59.000Z

242

Packaging and Transfer of Hazardous Materials and Materials of...  

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

PACKAGING AND TRANSFER OF HAZARDOUS MATERIALS AND MATERIALS OF NATIONAL SECURITY INTEREST Assessment Plan NNSANevada Site Office Facility Representative Division Performance...

243

MATERIAL CONTROL ACCOUNTING INMM  

SciTech Connect (OSTI)

Since 1996, the Mining and Chemical Combine (MCC - formerly known as K-26), and the United States Department of Energy (DOE) have been cooperating under the cooperative Nuclear Material Protection, Control and Accounting (MPC&A) Program between the Russian Federation and the U.S. Governments. Since MCC continues to operate a reactor for steam and electricity production for the site and city of Zheleznogorsk which results in production of the weapons grade plutonium, one of the goals of the MPC&A program is to support implementation of an expanded comprehensive nuclear material control and accounting (MC&A) program. To date MCC has completed upgrades identified in the initial gap analysis and documented in the site MC&A Plan and is implementing additional upgrades identified during an update to the gap analysis. The scope of these upgrades includes implementation of MCC organization structure relating to MC&A, establishing material balance area structure for special nuclear materials (SNM) storage and bulk processing areas, and material control functions including SNM portal monitors at target locations. Material accounting function upgrades include enhancements in the conduct of physical inventories, limit of error inventory difference procedure enhancements, implementation of basic computerized accounting system for four SNM storage areas, implementation of measurement equipment for improved accountability reporting, and both new and revised site-level MC&A procedures. This paper will discuss the implementation of MC&A upgrades at MCC based on the requirements established in the comprehensive MC&A plan developed by the Mining and Chemical Combine as part of the MPC&A Program.

Hasty, T.

2009-06-14T23:59:59.000Z

244

Optical limiting materials  

DOE Patents [OSTI]

Optical limiting materials. Methanofullerenes, fulleroids and/or other fullerenes chemically altered for enhanced solubility, in liquid solution, and in solid blends with transparent glass (SiO.sub.2) gels or polymers, or semiconducting (conjugated) polymers, are shown to be useful as optical limiters (optical surge protectors). The nonlinear absorption is tunable such that the energy transmitted through such blends saturates at high input energy per pulse over a wide range of wavelengths from 400-1100 nm by selecting the host material for its absorption wavelength and ability to transfer the absorbed energy into the optical limiting composition dissolved therein. This phenomenon should be generalizable to other compositions than substituted fullerenes.

McBranch, Duncan W. (Santa Fe, NM); Mattes, Benjamin R. (Santa Fe, NM); Koskelo, Aaron C. (Los Alamos, NM); Heeger, Alan J. (Santa Barbara, CA); Robinson, Jeanne M. (Los Alamos, NM); Smilowitz, Laura B. (Los Alamos, NM); Klimov, Victor I. (Los Alamos, NM); Cha, Myoungsik (Goleta, CA); Sariciftci, N. Serdar (Santa Barbara, CA); Hummelen, Jan C. (Groningen, NL)

1998-01-01T23:59:59.000Z

245

Materials for geothermal production  

SciTech Connect (OSTI)

Advances in the development of new materials continue to be made in the geothermal materials project. Many successes have already been accrued and the results used commercially. In FY 1991, work was focused on reducing well drilling, fluid transport and energy conversion costs. Specific activities performed included lightweight CO{sub 2}-resistant well cements, thermally conductive and scale resistant protective liner systems, chemical systems for lost circulation control, corrosion mitigation in process components at The Geysers, and elastomer-metal bonding systems. Efforts to transfer the technologies developed in these efforts to other energy-related sectors of the economy continued and considerable success was achieved.

Kukacka, L.E.

1992-01-01T23:59:59.000Z

246

Materials Under Extremes | ORNL  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: VegetationEquipment Surfaces andMapping the Nanoscale LandscapeImports 5.90Materials Porous Materials

247

Materials at the Mesoscale  

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 ResearchMaterials andMaterials

248

Materials for the Future  

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 ResearchMaterialsMaterials for

249

Container for radioactive materials  

DOE Patents [OSTI]

A container is claimed for housing a plurality of canister assemblies containing radioactive material. The several canister assemblies are stacked in a longitudinally spaced relation within a carrier to form a payload concentrically mounted within the container. The payload package includes a spacer for each canister assembly, said spacer comprising a base member longitudinally spacing adjacent canister assemblies from each other and sleeve surrounding the associated canister assembly for centering the same and conducting heat from the radioactive material in a desired flow path. 7 figures.

Fields, S.R.

1984-05-30T23:59:59.000Z

250

Short courses in Composite Materials  

E-Print Network [OSTI]

Short courses in Composite Materials Overview The ability to tailor the material properties used. Combining the adaptability of composites with clear weight savings, whilst tailoring materials properties Airbus and Glyndr University, the Advanced Composites Training and Development Centre educates current

Davies, John N.

251

Supercapacitors specialities - Materials review  

SciTech Connect (OSTI)

The electrode material is a key component for supercapacitor cell performance. As it is known, performance comparison of commercial available batteries and supercapacitors reveals significantly lower energy storage capability for supercapacitor devices. The energy density of commercial supercapacitor cells is limited to 10 Wh/kg whereas that of common lead acid batteries reaches 35-40 Wh/kg. For lithium ion batteries a value higher than 100 Wh/kg is easily available. Nevertheless, supercapacitors also known as ultracapacitors or electrochemical capacitors have other advantages in comparison with batteries. As a consequence, many efforts have been made in the last years to increase the storage energy density of electrochemical capacitors. A lot of results from published work (research and review papers, patents and reports) are available at this time. The purpose of this review is a presentation of the progress to date for the use of new materials and approaches for supercapacitor electrodes, with focus on the energy storage capability for practical applications. Many reported results refer to nanostructured carbon based materials and the related composites, used for the manufacture of experimental electrodes. A specific capacitance and a specific energy are seldom revealed as the main result of the performed investigation. Thus for nanoprous (activated) carbon based electrodes a specific capacitance up to 200-220 F/g is mentioned for organic electrolyte, whereas for aqueous electrolyte, the value is limited to 400-500 F/g. Significant contribution to specific capacitance is possible from fast faradaic reactions at the electrode-electrolyte interface in addition to the electric double layer effect. The corresponding energy density is limited to 30-50 Wh/kg for organic electrolyte and to 12-17 Wh/kg for aqueous electrolyte. However such performance indicators are given only for the carbon material used in electrodes. For a supercapacitor cell, where two electrodes and also other materials for cell assembling and packaging are used, the above mentioned values have to be divided by a factor higher than four. As a consequence, the specific energy of a prototype cell, hardly could exceed 10 Wh/kg because of difficulties with the existing manufacturing technology. Graphene based materials and carbon nanotubes and different composites have been used in many experiments reported in the last years. Nevertheless in spite of the outstanding properties of these materials, significant increase of the specific capacitance or of the specific energy in comparison with activated or nanoporous carbon is not achieved. Use of redox materials as metal oxides or conducting polymers in combination with different nanostructured carbon materials (nanocomposite electrodes) has been found to contribute to further increase of the specific capacitance or of the specific energy. Nevertheless, few results are reported for practical cells with such materials. Many results are reported only for a three electrode system and significant difference is possible when the electrode is used in a practical supercapacitor cell. Further improvement in the electrode manufacture and more experiments with supercapacitor cells with the known electrochemical storage materials are required. Device prototypes and commercial products with an energy density towards 15-20 Wh/kg could be realized. These may be a milestone for further supercapacitor device research and development, to narrow the storage energy gap between batteries and supercapacitors.

Obreja, Vasile V. N. [National Research and Development Institute for Microtechnologies (IMT-Bucuresti), Bucharest, 126A Erou Iancu Nicolae Street, 077190 (Romania)

2014-06-16T23:59:59.000Z

252

Vibrational Damping of Composite Materials  

E-Print Network [OSTI]

the damping material and epoxy resin. The surface of theinfiltration of the epoxy resin into the damping materialthe damping material and resin (epoxy) is occurring and is

Biggerstaff, Janet M.

2006-01-01T23:59:59.000Z

253

Materials and Manufacturing  

E-Print Network [OSTI]

Environmental Assurance Anne Meinhold Unprecedented Accomplishments in the Use of Aluminum-Lithium Alloy Preston is the solution. Other times, the design must accommodate the limitations of materials properties. The design requirements, and written procedures. Nondestructive testing depends on incident or input energy that interacts

254

Supplemental Material Supplemental methods  

E-Print Network [OSTI]

Material (ESI) for Integrative Biology This journal is © The Royal Society of Chemistry 2009 #12;Computing counter and % ID/g calculated as (counts/weight tissue)/ total counts injected. Mass Spectrometry. To extract ACPPs to obtain electrospray (ESI) mass spectra, a solution of 9M guanidinium chloride (Gu

Tsien, Roger Y.

255

Materials Safety Data Sheets  

E-Print Network [OSTI]

Materials Safety Data Sheets (MSDS) MSDS contain chemical hazard information about substances compounds and solvents. MSDS data can be accessed from the following URLs http://www.ehs.umass.edu/ http://www.chem.umass.edu/Safety the "Important Safety Sites for the University" link to reach a variety of safety related information, including

Schweik, Charles M.

256

NMR imaging of materials  

SciTech Connect (OSTI)

Interest in the area of NMR imaging has been driven by the widespread success of medical imaging. John M. Listerud of the Pendergrass Diagnostic Research Laboratories, Steven W. Sinton of Lockheed, and Gary P. Drobny of the University of Washington describe the principal image reconstruction methods, factors limiting spatial resolution, and applications of imaging to the study of materials.

Listerud, J.M.; Sinton, S.W.; Drobny, G.P.

1989-01-01T23:59:59.000Z

257

Sustainable Materials Course Outline  

E-Print Network [OSTI]

, embodied energy; environmental footprint, waste recycling and pollution minimization, life cycle assessment Science and Engineering (Building E8) Phone: 9385 5025 j.q.zhang@unsw.edu.au Consultation hours: by appointment To be advised School of Materials Science and Engineering (Building E8) Consultation hours

New South Wales, University of

258

Action Plan Materials Science  

E-Print Network [OSTI]

sense, including all strata) has available to it a wide range of con- venient products which improve, improving companies' pros- pects and generating wealth without harming the environment. And allAction Plan 2010-2013 Materials Science Area EXECUTIVE SUMMARY #12;N.B.: If you require any further

Fitze, Patrick

259

From Smart Materials to Cognitive Materials Requirements and Challenges  

E-Print Network [OSTI]

From Smart Materials to Cognitive Materials ­ Requirements and Challenges Lutz Frommberger (lutz construction, production engineer- ing, or wearable computing. Smart and sensorial materials provide a variety this application than the material itself that can be considered being "smart". In this contribution, we proceed

Bremen, Universität

260

Graphene: Materially Better Carbon  

SciTech Connect (OSTI)

Graphene, a single atomthick plane of carbon atoms arranged in a honeycomb lattice, has captivated the attention of physicists, materials scientists, and engineers alike over the five years following its experimental isolation. Graphene is a fundamentally new type of electronic material whose electrons are strictly confined to a two-dimensional plane and exhibit properties akin to those of ultrarelativistic particles. Graphene's two-dimensional form suggests compatibility with conventional wafer processing technology. Extraordinary physical properties, including exceedingly high charge carrier mobility, current-carrying capacity, mechanical strength, and thermal conductivity, make it an enticing candidate for new electronic technologies both within and beyond complementary metal oxide semiconductors (CMOS). Immediate graphene applications include high-speed analog electronics and highly conductive, flexible, transparent thin films for displays and optoelectronics. Currently, much graphene research is focused on generating and tuning a bandgap and on novel device structures that exploit graphene's extraordinary electrical, optical, and mechanical properties.

Fuhrer, M. S.; Lau, C. N.; MacDonald, A. H.

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "weapons-usable fissile materials" 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

Geothermal materials development activities  

SciTech Connect (OSTI)

This ongoing R&D program is a part of the Core Research Category of the Department of Energy/Geothermal Division initiative to accelerate the utilization of geothermal resources. High risk materials problems that if successfully solved will result in significant reductions in well drilling, fluid transport and energy conversion costs, are emphasized. The project has already developed several advanced materials systems that are being used by the geothermal industry and by Northeastern Electric, Gas and Steam Utilities. Specific topics currently being addressed include lightweight C0{sub 2}-resistant well cements, thermally conductive scale and corrosion resistant liner systems, chemical systems for lost circulation control, elastomer-metal bonding systems, and corrosion mitigation at the Geysers. Efforts to enhance the transfer of the technologies developed in these activities to other sectors of the economy are also underway.

Kukacka, L.E.

1993-06-01T23:59:59.000Z

262

Webinar: Hydrogen Compatibility of Materials  

Broader source: Energy.gov [DOE]

Video recording of the webinar titled, Hydrogen Compatibility of Materials, originally presented on August 13, 2013.

263

Cathode material for lithium batteries  

DOE Patents [OSTI]

A method of manufacture an article of a cathode (positive electrode) material for lithium batteries. The cathode material is a lithium molybdenum composite transition metal oxide material and is prepared by mixing in a solid state an intermediate molybdenum composite transition metal oxide and a lithium source. The mixture is thermally treated to obtain the lithium molybdenum composite transition metal oxide cathode material.

Park, Sang-Ho; Amine, Khalil

2013-07-23T23:59:59.000Z

264

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

265

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

266

MATERIAL HANDLING, STORAGE, AND DISPOSAL  

E-Print Network [OSTI]

Materials shall be stored in a manner that allows easy identification and access to labels, identification entering storage areas. All persons shall be in a safe position while materials are being loadedEM 385-1-1 XX Jun 13 14-1 SECTION 14 MATERIAL HANDLING, STORAGE, AND DISPOSAL 14.A MATERIAL

US Army Corps of Engineers

267

George Smith, Department of Materials,  

E-Print Network [OSTI]

George Smith, Department of Materials, Oxford University, Parks Road, Oxford OX1 3PH UK Email: george.smith@materials.ox.ac.uk URL: www.materials.ox.ac.uk The aims of the Department of Materials experienced one of the most successful years in its 46-year history, says head of department George Smith. Top

Paxton, Anthony T.

268

Materials in design  

E-Print Network [OSTI]

the strength, hardness and wear resistance has been increased. S rin Materials Since in many cases equipment requires that springs have to operate properly at conditions of excessive vibration, corrosive environment, extremes temperatures. A great care has...) It is considered a good long wearing bearing metal where good bearing conditions are present once the design has been done very good. (Accurate filling, good oil clearance; good lubrication, non-corrosive oil). It can be used with hardened shafts. B ' g B Tin...

Perata, Alfredo Ferando

1970-01-01T23:59:59.000Z

269

Materials Technical Team Roadmap  

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 AccidentEnergy Objective: DevelopMaterials

270

Materials | 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 AccidentEnergy Objective:11 DOEMaterials Materials

271

Lead carbonate scintillator materials  

DOE Patents [OSTI]

Improved radiation detectors containing lead carbonate or basic lead carbonate as the scintillator element are disclosed. Both of these scintillators have been found to provide a balance of good stopping power, high light yield and short decay constant that is superior to other known scintillator materials. The radiation detectors disclosed are favorably suited for use in general purpose detection and in medical uses. 3 figures.

Derenzo, S.E.; Moses, W.W.

1991-05-14T23:59:59.000Z

272

Advanced Materials Manufacturing | ORNL  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth (AOD)ProductssondeadjustsondeadjustAbout the BuildingInnovation Portal Advanced Material

273

Scalable Routes to Efficient Thermoelectric Materials  

E-Print Network [OSTI]

thermoelectric materials consisting of epitaxially-grownefficient thermoelectric materials," Nature, vol. 451, pp.superlattice thermoelectric materials and devices," Science,

Feser, Joseph Patrick

2010-01-01T23:59:59.000Z

274

Advanced Battery Materials Characterization: Success stories...  

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

Advanced Battery Materials Characterization: Success stories from the High Temperature Materials Laboratory (HTML) User Program Advanced Battery Materials Characterization: Success...

275

Materials Research in the Information Age  

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

Materials Research in the Information Age Accelerating Advanced Material Development NERSC Science Gateway a 'Google of Material Properties' October 31, 2011 | Tags: Materials...

276

RFI: DOE Materials Strategy | Department of Energy  

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

RFI: DOE Materials Strategy RFI: DOE Materials Strategy DOE Materials Strategy - request for information RFI: DOE Materials Strategy More Documents & Publications Microsoft Word -...

277

Sandia National Laboratories: Light Creation Materials  

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

TechnologiesLight Creation Materials Light Creation Materials Overview of SSL Light Creation Materials Different families of inorganic semiconductor materials can...

278

Sandia National Laboratories: Light Creation Materials  

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

EFRCOverviewLight Creation Materials Light Creation Materials Overview of SSL Light Creation Materials Different families of inorganic semiconductor materials can contribute to...

279

Cathode materials review  

SciTech Connect (OSTI)

The electrochemical potential of cathode materials defines the positive side of the terminal voltage of a battery. Traditionally, cathode materials are the energy-limiting or voltage-limiting electrode. One of the first electrochemical batteries, the voltaic pile invented by Alessandro Volta in 1800 (Phil. Trans. Roy. Soc. 90, 403-431) had a copper-zinc galvanic element with a terminal voltage of 0.76 V. Since then, the research community has increased capacity and voltage for primary (nonrechargeable) batteries and round-trip efficiency for secondary (rechargeable) batteries. Successful secondary batteries have been the lead-acid with a lead oxide cathode and a terminal voltage of 2.1 V and later the NiCd with a nickel(III) oxide-hydroxide cathode and a 1.2 V terminal voltage. The relatively low voltage of those aqueous systems and the low round-trip efficiency due to activation energies in the conversion reactions limited their use. In 1976, Wittingham (J. Electrochem. Soc., 123, 315) and Besenhard (J. Power Sources 1(3), 267) finally enabled highly reversible redox reactions by intercalation of lithium ions instead of by chemical conversion. In 1980, Goodenough and Mizushima (Mater. Res. Bull. 15, 783-789) demonstrated a high-energy and high-power LiCoO{sub 2} cathode, allowing for an increase of terminal voltage far beyond 3 V. Over the past four decades, the international research community has further developed cathode materials of many varieties. Current state-of-the-art cathodes demonstrate voltages beyond any known electrolyte stability window, bringing electrolyte research once again to the forefront of battery research.

Daniel, Claus, E-mail: danielc@ornl.gov; Mohanty, Debasish, E-mail: danielc@ornl.gov; Li, Jianlin, E-mail: danielc@ornl.gov; Wood, David L., E-mail: danielc@ornl.gov [Oak Ridge National Laboratory, 1 Bethel Valley Road, MS6472 Oak Ridge, TN 37831-6472 (United States)

2014-06-16T23:59:59.000Z

280

Combinatorial synthesis of novel materials  

DOE Patents [OSTI]

Methods and apparatus for the preparation and use of a substrate having an array of diverse materials in predefined regions thereon. A substrate having an array of diverse materials thereon is generally prepared by delivering components of materials to predefined regions on a substrate, and simultaneously reacting the components to form at least two materials. Materials which can be prepared using the methods and apparatus of the present invention include, for example, covalent network solids, ionic solids and molecular solids. More particularly, materials which can be prepared using the methods and apparatus of the present invention include, for example, inorganic materials, intermetallic materials, metal alloys, ceramic materials, organic materials, organometallic materials, non-biological organic polymers, composite materials (e.g., inorganic composites, organic composites, or combinations thereof), etc. Once prepared, these materials can be screened for useful properties including, for example, electrical, thermal, mechanical, morphological, optical, magnetic, chemical, or other properties. Thus, the present invention provides methods for the parallel synthesis and analysis of novel materials having useful properties.

Schultz, Peter G. (Oakland, CA); Xiang, Xiaodong (Alameda, CA); Goldwasser, Isy (Menlo Park, CA)

2001-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "weapons-usable fissile materials" 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

Combinatorial synthesis of novel materials  

DOE Patents [OSTI]

Methods and apparatus for the preparation and use of a substrate having an array of diverse materials in predefined regions thereon. A substrate having an array of diverse materials thereon is generally prepared by delivering components of materials to predefined regions on a substrate, and simultaneously reacting the components to form at least two materials. Materials which can be prepared using the methods and apparatus of the present invention include, for example, covalent network solids, ionic solids and molecular solids. More particularly, materials which can be prepared using the methods and apparatus of the present invention include, for example, inorganic materials, intermetallic materials, metal alloys, ceramic materials, organic materials, organometallic materials, non-biological organic polymers, composite materials (e.g., inorganic composites, organic composites, or combinations thereof), etc. Once prepared, these materials can be screened for useful properties including, for example, electrical, thermal, mechanical, morphological, optical, magnetic, chemical, or other properties. Thus, the present invention provides methods for the parallel synthesis and analysis of novel materials having useful properties.

Schultz, Peter G. (Oakland, CA); Xiang, Xiaodong (Alameda, CA); Goldwasser, Isy (Alameda, CA)

2002-02-12T23:59:59.000Z

282

Combinatorial synthesis of novel materials  

DOE Patents [OSTI]

Methods and apparatus for the preparation and use of a substrate having an array of diverse materials in predefined regions thereon. A substrate having an array of diverse materials thereon is generally prepared by delivering components of materials to predefined regions on a substrate, and simultaneously reacting the components to form at least two materials. Materials which can be prepared using the methods and apparatus of the present invention include, for example, covalent network solids, ionic solids and molecular solids. More particularly, materials which can be prepared using the methods and apparatus of the present invention include, for example, inorganic materials, intermetallic materials, metal alloys, ceramic materials, organic materials, organometallic materials, non-biological organic polymers, composite materials (e.g., inorganic composites, organic composites, or combinations thereof), etc. Once prepared, these materials can be screened for useful properties including, for example, electrical, thermal, mechanical, morphological, optical, magnetic, chemical, or other properties. Thus, the present invention provides methods for the parallel synthesis and analysis of novel materials having useful properties.

Schultz, Peter G. (Oakland, CA); Xiang, Xiaodong (Alameda, CA); Goldwasser, Isy (Menlo Park, CA)

1999-12-21T23:59:59.000Z

283

Combinatorial sythesis of organometallic materials  

DOE Patents [OSTI]

Methods and apparatus for the preparation and use of a substrate having an array of diverse materials in predefined regions thereon. A substrate having an array of diverse materials thereon is generally prepared by delivering components of materials to predefined regions on a substrate, and simultaneously reacting the components to form at least two materials. Materials which can be prepared using the methods and apparatus of the present invention include, for example, covalent network solids, ionic solids and molecular solids. More particularly, materials which can be prepared using the methods and apparatus of the present invention include, for example, inorganic materials, intermetallic materials, metal alloys, ceramic materials, organic materials, organometallic materials, non-biological organic polymers, composite materials (e.g., inorganic composites, organic composites, or combinations thereof), etc. Once prepared, these materials can be screened for useful properties including, for example, electrical, thermal, mechanical, morphological, optical, magnetic, chemical, or other properties. Thus, the present invention provides methods for the parallel synthesis and analysis of novel materials having useful properties.

Schultz, Peter G. (Oakland, CA); Xiang, Xiaodong (Alameda, CA); Goldwasser, Isy (Alameda, CA)

2002-07-16T23:59:59.000Z

284

Optical limiting materials  

DOE Patents [OSTI]

Methanofullerenes, fulleroids and/or other fullerenes chemically altered for enhanced solubility, in liquid solution, and in solid blends with transparent glass (SiO{sub 2}) gels or polymers, or semiconducting (conjugated) polymers, are shown to be useful as optical limiters (optical surge protectors). The nonlinear absorption is tunable such that the energy transmitted through such blends saturates at high input energy per pulse over a wide range of wavelengths from 400--1,100 nm by selecting the host material for its absorption wavelength and ability to transfer the absorbed energy into the optical limiting composition dissolved therein. This phenomenon should be generalizable to other compositions than substituted fullerenes. 5 figs.

McBranch, D.W.; Mattes, B.R.; Koskelo, A.C.; Heeger, A.J.; Robinson, J.M.; Smilowitz, L.B.; Klimov, V.I.; Cha, M.; Sariciftci, N.S.; Hummelen, J.C.

1998-04-21T23:59:59.000Z

285

Synthesis of refractory materials  

DOE Patents [OSTI]

Refractory metal nitrides are synthesized during a self-propagating combustion process utilizing a solid source of nitrogren. For this purpose, a metal azide is employed, preferably NaN.sub.3. The azide is combusted with Mg or Ca, and a metal oxide is selected from Groups III-A, IV-A, III-B, IV-B, or a rare earth metal oxide. The mixture of azide, Ca or Mg and metal oxide is heated to the mixture's ignition temperature. At that temperature the mixture is ignited and undergoes self-sustaining combustion until the starter materials are exhausted, producing the metal nitride.

Holt, Joseph B. (San Jose, CA)

1984-01-01T23:59:59.000Z

286

Synthesis of refractory materials  

DOE Patents [OSTI]

Refractory metal nitrides are synthesized during a self-propagating combustion process utilizing a solid source of nitrogen. For this purpose, a metal azide is employed, preferably NaN/sub 3/. The azide is combusted with Mg or Ca, and a metal oxide is selected from Groups III-A, IV-A, III-B, IV-B, or a rare earth metal oxide. The mixture of azide, Ca or Mg and metal oxide is heated to the mixture's ignition temperature. At that temperature the mixture is ignited and undergoes self-sustaining combustion until the starter materials are exhausted, producing the metal nitride.

Holt, J.B.

1983-08-16T23:59:59.000Z

287

Construction Material And Method  

DOE Patents [OSTI]

A structural material of a polystyrene base and the reaction product of the polystyrene base and a solid phosphate ceramic. The ceramic is applied as a slurry which includes one or more of a metal oxide or a metal hydroxide with a source of phosphate to produce a phosphate ceramic and a poly (acrylic acid or acrylate) or combinations or salts thereof and polystyrene or MgO applied to the polystyrene base and allowed to cure so that the dried aqueous slurry chemically bonds to the polystyrene base. A method is also disclosed of applying the slurry to the polystyrene base.

Wagh, Arun S. (Orland Park, IL); Antink, Allison L. (Bolingbrook, IL)

2006-02-21T23:59:59.000Z

288

Careers | Critical Materials Institute  

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 to someone6Energy,MUSEUM DISPLAYCareers The Critical Materials Institute

289

LANL: Materials Science Laboratory  

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

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290

Work with Biological Materials  

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

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291

Work with Biological 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 MayAtmosphericNuclear SecurityTensile Strain Switched FerromagnetismWaste and MaterialsWenjun1 Table 1.14 Sales of4)Delegations, andARMWork

292

Magnetic Materials (MM)  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: VegetationEquipment Surfaces and InterfacesAdministration -Lowell L.FallU . S .ofFieldMagnetic Materials

293

Material Point Methods  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: VegetationEquipment Surfaces andMapping the Nanoscale LandscapeImports 5.90 4.86 4.77of PolarMaterial

294

Material Safety Data Sheet  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: VegetationEquipment Surfaces andMapping the Nanoscale LandscapeImports 5.90 4.86 4.77ofMaterial Safety

295

Materials/Condensed Matter  

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 selectedContractMaterials/Condensed Matter Print

296

Materials/Condensed Matter  

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 selectedContractMaterials/Condensed Matter

297

Material efficiency in construction  

E-Print Network [OSTI]

, this generation must change its use of energy and materials. 1.1 The need to reduce carbon dioxide emissions The Fifth Assessment Report of the Intergovernmental Panel on Climate Change (IPCC) states as #16;unequivocal#17; that the Earth's atmosphere and oceans... in order to save energy and carbon. University of Cambridge, Cambridge, UK. ISBN 978-0- 903428-32-3 3. Allwood, J.M., Cullen, J.M., Patel, A.C.H., Cooper, D.R.,Moynihan, M.C., Milford, R.L., Carruth, M.A. and McBrien, M. 2011. Prolonging our metal life #22...

Moynihan, Muiris

2014-10-07T23:59:59.000Z

298

Laser Plasma Material Interactions  

SciTech Connect (OSTI)

Surface treatment by means of pulsed laser beams in reactive atmospheres is an attractive technique to enhance the surface features, such as corrosion and wear resistance or the hardness. Many carbides and nitrides play an important role for technological applications, requiring the mentioned property improvements. Here we present a new promising fast, flexible and clean technique for a direct laser synthesis of carbide and nitride surface films by short pulsed laser irradiation in reactive atmospheres (e.g. methane, nitrogen). The corresponding material is treated by short intense laser pulses involving plasma formation just above the irradiated surface. Gas-Plasma-Surface reactions lead to a fast incorporation of the gas species into the material and subsequently the desired coating formation if the treatment parameters are chosen properly. A number of laser types have been used for that (Excimer Laser, Nd:YAG, Ti:sapphire, Free Electron Laser) and a number of different nitride and carbide films have been successfully produced. The mechanisms and some examples will be presented for Fe treated in nitrogen and Si irradiated in methane.

Schaaf, Peter; Carpene, Ettore [Universitaet Goettingen, II. Physikalisches Institut, Friedrich-Hund-Platz 1, 37077 Goettingen (Germany)

2004-12-01T23:59:59.000Z

299

Additive assembly of digital materials  

E-Print Network [OSTI]

This thesis develops the use of additive assembly of press-fit digital materials as a new rapid-prototyping process. Digital materials consist of a finite set of parts that have discrete connections and occupy discrete ...

Ward, Jonathan (Jonathan Daniel)

2010-01-01T23:59:59.000Z

300

STRUCTURAL ENGINEERING, MECHANICS AND MATERIALS  

E-Print Network [OSTI]

of companies worldwide; cladding effects on, and hybrid control of, the response of tall buildings Buildings Masonry Structures Nano/Microstructure of Cement-based Materials Polymeric Composite Systems Reliable Engineering Computing Risk Analysis Seismic Hazard Mitigation Smart Materials

Wang, Yuhang

Note: This page contains sample records for the topic "weapons-usable fissile materials" 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

DPC materials and corrosion environments  

SciTech Connect (OSTI)

This review focuses on the performance of basket materials that could be exposed to ground water over thousands of years, and prospective disposal overpack materials that could possibly be used to protect dual-purpose canisters (DPCs) in disposal environments.

Ilgen, Anastasia G.; Bryan, Charles R.; Stephanie Teich-McGoldrick; Ernest Hardin

2014-10-01T23:59:59.000Z

302

FURTHERING THE RECLAIMED MATERIALS EXPERIENCE  

E-Print Network [OSTI]

A comprehensive study of the reclaimed materials industry and ways it could be improved from a management standpoint by working through a Design Management problem solving approach. Project Objectives: To improve the sourcing of reclaimed materials...

Bartels, Robert A.

2012-08-31T23:59:59.000Z

303

Management of Transuranic Contaminated Material  

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

To establish guidelines for the generation, treatment, packaging, storage, transportation, and disposal of transuranic (TRU) contaminated material.

1982-09-30T23:59:59.000Z

304

Thermoelectric Materials, Devices and Systems:  

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

-DRAFT - FOR OFFICIAL USE ONLY - DRAFT Thermoelectric Materials, Devices and Systems: 1 Technology Assessment 2 Contents 3 1. Thermoelectric Generation ......

305

Sandia National Laboratories: Materials Science  

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

Facilities, Materials Science, News, News & Events, Research & Capabilities, Solid-State Lighting Semiconductor nanowire lasers have attracted intense interest as...

306

Webinar: Hydrogen Storage Materials Requirements  

Broader source: Energy.gov [DOE]

Video recording and text version of the webinar titled, Hydrogen Storage Materials Requirements, originally presented on June 25, 2013.

307

Corrosion resistant ceramic materials  

DOE Patents [OSTI]

Ceramic materials are disclosed which exhibit stability in severely-corrosive environments having high alkali-metal activity, high sulfur/sulfide activity and/or molten halides at temperatures of 200--550 C or organic salt (including SO{sub 2} and SO{sub 2}Cl{sub 2}) at temperatures of 25--200 C. These sulfide ceramics form stoichiometric (single-phase) compounds with sulfides of Ca, Li, Na, K, Al, Mg, Si, Y, La, Ce, Ga, Ba, Zr and Sr and show melting-points that are sufficiently low and have excellent wettability with many metals (Fe, Ni, Mo) to easily form metal/ceramic seals. Ceramic compositions are also formulated to adequately match thermal expansion coefficient of adjacent metal components. 1 fig.

Kaun, T.D.

1996-07-23T23:59:59.000Z

308

Corrosion resistant ceramic materials  

DOE Patents [OSTI]

Ceramic materials which exhibit stability in severely-corrosive environments having high alkali-metal activity, high sulfur/sulfide activity and/or molten halides at temperatures of 200.degree.-550.degree. C. or organic salt (including SO.sub.2 and SO.sub.2 Cl.sub.2) at temperatures of 25.degree.-200.degree. C. These sulfide ceramics form stoichiometric (single-phase) compounds with sulfides of Ca, Li, Na, K, Al, Mg, Si, Y, La, Ce, Ga, Ba, Zr and Sr and show melting-points that are sufficiently low and have excellent wettability with many metals (Fe, Ni, Mo) to easily form metal/ceramic seals. Ceramic compositions are also formulated to adequately match thermal expansion coefficient of adjacent metal components.

Kaun, Thomas D. (320 Willow St., New Lenox, IL 60451)

1995-01-01T23:59:59.000Z

309

Corrosion resistant ceramic materials  

DOE Patents [OSTI]

Ceramic materials which exhibit stability in severely-corrosive environments having high alkali-metal activity, high sulfur/sulfide activity and/or molten halides at temperatures of 200.degree.-550.degree. C. or organic salt (including SO.sub.2 and SO.sub.2 Cl.sub.2) at temperatures of 25.degree.-200.degree. C. These sulfide ceramics form stoichiometric (single-phase) compounds with sulfides of Ca, Li, Na, K, Al, Mg, Si, Y, La, Ce, Ga, Ba, Zr and Sr and show melting-points that are sufficiently low and have excellent wettability with many metals (Fe, Ni, Mo) to easily form metal/ceramic seals. Ceramic compositions are also formulated to adequately match thermal expansion coefficient of adjacent metal components.

Kaun, Thomas D. (320 Willow St., New Lenox, IL 60451)

1996-01-01T23:59:59.000Z

310

Combinatorial synthesis of ceramic materials  

DOE Patents [OSTI]

A combinatorial library includes a gelcast substrate defining a plurality of cavities in at least one surface thereof; and a plurality of gelcast test materials in the cavities, at least two of the test materials differing from the substrate in at least one compositional characteristic, the two test materials differing from each other in at least one compositional characteristic.

Lauf, Robert J.; Walls, Claudia A.; Boatner, Lynn A.

2006-11-14T23:59:59.000Z

311

Combinatorial synthesis of ceramic materials  

DOE Patents [OSTI]

A combinatorial library includes a gelcast substrate defining a plurality of cavities in at least one surface thereof; and a plurality of gelcast test materials in the cavities, at least two of the test materials differing from the substrate in at least one compositional characteristic, the two test materials differing from each other in at least one compositional characteristic.

Lauf, Robert J. (Oak Ridge, TN) [Oak Ridge, TN; Walls, Claudia A. (Oak Ridge, TN) [Oak Ridge, TN; Boatner, Lynn A. (Oak Ridge, TN) [Oak Ridge, TN

2010-02-23T23:59:59.000Z

312

Preparation of asymmetric porous materials  

DOE Patents [OSTI]

A method for preparing an asymmetric porous material by depositing a porous material film on a flexible substrate, and applying an anisotropic stress to the porous media on the flexible substrate, where the anisotropic stress results from a stress such as an applied mechanical force, a thermal gradient, and an applied voltage, to form an asymmetric porous material.

Coker, Eric N. (Albuquerque, NM)

2012-08-07T23:59:59.000Z

313

Nanostructured materials for hydrogen storage  

DOE Patents [OSTI]

A system for hydrogen storage comprising a porous nano-structured material with hydrogen absorbed on the surfaces of the porous nano-structured material. The system of hydrogen storage comprises absorbing hydrogen on the surfaces of a porous nano-structured semiconductor material.

Williamson, Andrew J. (Pleasanton, CA); Reboredo, Fernando A. (Pleasanton, CA)

2007-12-04T23:59:59.000Z

314

Frontiers of Fusion Materials Science  

E-Print Network [OSTI]

migration Radiation damage accumulation kinetics · 1 D vs. 3D diffusion processes · ionization Insulators · Optical Materials *asterisk denotes Fusion Materials Task Group #12;Fusion Materials Sciences R Displacement cascades Quantification of displacement damage source term · Is the concept of a liquid valid

315

Department of Advanced Materials Science  

E-Print Network [OSTI]

@k.u-tokyo.ac.jpe-mail 04-7136-3781T E L Environmental-friendly materials process, Metal smelting and re ning process of Advanced Materials Science masashi@issp.u-tokyo.ac.jpe-mail 04-7136-3225T E L Nuclear magnetic resonance New Materials Synthesis, Superconductivity, Quantum Spin Liquid,Topological Hall Effect takatama

Katsumoto, Shingo

316

Materials Performance in USC Steam  

SciTech Connect (OSTI)

Materials Performance in USC Steam: (1) pressure effects on steam oxidation - unique capability coming on-line; (2) hydrogen evolution - hydrogen permeability apparatus to determine where hydrogen goes during steam oxidation; and (3) NETL materials development - steam oxidation resource for NETL developed materials.

G. R. Holcomb; J. Tylczak; G. H. Meier; N. M. Yanar

2011-09-07T23:59:59.000Z

317

Fission meter and neutron detection using poisson distribution comparison  

DOE Patents [OSTI]

A neutron detector system and method for discriminating fissile material from non-fissile material wherein a digital data acquisition unit collects data at high rate, and in real-time processes large volumes of data directly into information that a first responder can use to discriminate materials. The system comprises counting neutrons from the unknown source and detecting excess grouped neutrons to identify fission in the unknown source. Comparison of the observed neutron count distribution with a Poisson distribution is performed to distinguish fissile material from non-fissile material.

Rowland, Mark S; Snyderman, Neal J

2014-11-18T23:59:59.000Z

318

Mathematical modelings of smart materials and structures  

E-Print Network [OSTI]

Mathematical modelings of smart materials and structures Christian Licht , Thibaut Weller mathematical models of smart materials and smart structures. Smart materials are materials which present perturbations methods, asymptotic analysis, plates and rods models. 1 Introduction Smart materials present

Paris-Sud XI, Université de

319

Microwavable thermal energy storage material  

DOE Patents [OSTI]

A microwavable thermal energy storage material is provided which includes a mixture of a phase change material and silica, and a carbon black additive in the form of a conformable dry powder of phase change material/silica/carbon black, or solid pellets, films, fibers, moldings or strands of phase change material/high density polyethylene/ethylene-vinyl acetate/silica/carbon black which allows the phase change material to be rapidly heated in a microwave oven. The carbon black additive, which is preferably an electrically conductive carbon black, may be added in low concentrations of from 0.5 to 15% by weight, and may be used to tailor the heating times of the phase change material as desired. The microwavable thermal energy storage material can be used in food serving applications such as tableware items or pizza warmers, and in medical wraps and garments.

Salyer, Ival O. (Dayton, OH)

1998-09-08T23:59:59.000Z

320

Microwavable thermal energy storage material  

DOE Patents [OSTI]

A microwavable thermal energy storage material is provided which includes a mixture of a phase change material and silica, and a carbon black additive in the form of a conformable dry powder of phase change material/silica/carbon black, or solid pellets, films, fibers, moldings or strands of phase change material/high density polyethylene/ethylene vinyl acetate/silica/carbon black which allows the phase change material to be rapidly heated in a microwave oven. The carbon black additive, which is preferably an electrically conductive carbon black, may be added in low concentrations of from 0.5 to 15% by weight, and may be used to tailor the heating times of the phase change material as desired. The microwavable thermal energy storage material can be used in food serving applications such as tableware items or pizza warmers, and in medical wraps and garments. 3 figs.

Salyer, I.O.

1998-09-08T23:59:59.000Z

Note: This page contains sample records for the topic "weapons-usable fissile materials" 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

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.

322

Fossil energy materials needs assessment  

SciTech Connect (OSTI)

An assessment of needs for materials of construction for fossil energy systems was prepared by ORNL staff members who conducted a literature search and interviewed various individuals and organizations that are active in the area of fossil energy technology. Critical materials problems associated with fossil energy systems are identified. Background information relative to the various technologies is given and materials research needed to enhance the viability and improve the economics of fossil energy processes is discussed. The assessment is presented on the basis of materials-related disciplines that impact fossil energy material development. These disciplines include the design-materials interface, materials fabrication technology, corrosion and materials compatibility, wear phenomena, ceramic materials, and nondestructive testing. The needs of these various disciplines are correlated with the emerging fossil energy technologies that require materials consideration. Greater emphasis is given to coal technology - particularly liquefaction, gasification, and fluidized bed combustion - than to oil and gas technologies because of the perceived inevitability of US dependence on coal conversion and utilization systems as a major part of our total energy production.

King, R.T.; Judkins, R.R. (comps.)

1980-07-01T23:59:59.000Z

323

Catalyzed Ceramic Burner Material  

SciTech Connect (OSTI)

Catalyzed combustion offers the advantages of increased fuel efficiency, decreased emissions (both NOx and CO), and an expanded operating range. These performance improvements are related to the ability of the catalyst to stabilize a flame at or within the burner media and to combust fuel at much lower temperatures. This technology has a diverse set of applications in industrial and commercial heating, including boilers for the paper, food and chemical industries. However, wide spread adoption of catalyzed combustion has been limited by the high cost of precious metals needed for the catalyst materials. The primary objective of this project was the development of an innovative catalyzed burner media for commercial and small industrial boiler applications that drastically reduce the unit cost of the catalyzed media without sacrificing the benefits associated with catalyzed combustion. The scope of this program was to identify both the optimum substrate material as well as the best performing catalyst construction to meet or exceed industry standards for durability, cost, energy efficiency, and emissions. It was anticipated that commercial implementation of this technology would result in significant energy savings and reduced emissions. Based on demonstrated achievements, there is a potential to reduce NOx emissions by 40,000 TPY and natural gas consumption by 8.9 TBtu in industries that heavily utilize natural gas for process heating. These industries include food manufacturing, polymer processing, and pulp and paper manufacturing. Initial evaluation of commercial solutions and upcoming EPA regulations suggests that small to midsized boilers in industrial and commercial markets could possibly see the greatest benefit from this technology. While out of scope for the current program, an extension of this technology could also be applied to catalytic oxidation for volatile organic compounds (VOCs). Considerable progress has been made over the course of the grant period in accomplishing these objectives. Our work in the area of Pd-based, methane oxidation catalysts has led to the development of highly active catalysts with relatively low loadings of Pd metal using proprietary coating methods. The thermal stability of these Pd-based catalysts were characterized using SEM and BET analyses, further demonstrating that certain catalyst supports offer enhanced stability toward both PdO decomposition and/or thermal sintering/growth of Pd particles. When applied to commercially available fiber mesh substrates (both metallic and ceramic) and tested in an open-air burner, these catalyst-support chemistries showed modest improvements in the NOx emissions and radiant output compared to uncatalyzed substrates. More significant, though, was the performance of the catalyst-support chemistries on novel media substrates. These substrates were developed to overcome the limitations that are present with commercially available substrate designs and increase the gas-catalyst contact time. When catalyzed, these substrates demonstrated a 65-75% reduction in NOx emissions across the firing range when tested in an open air burner. In testing in a residential boiler, this translated into NOx emissions of <15 ppm over the 15-150 kBtu/hr firing range.

Barnes, Amy S., Dr.

2012-06-29T23:59:59.000Z

324

fmd  

National Nuclear Security Administration (NNSA)

uranium have become surplus to the defense needs of both the United States and Russia. The Office of Fissile Materials Disposition (FMD) plays an important role in...

325

At DOE, nonproliferation sinks despite its success  

SciTech Connect (OSTI)

Milestones are slipping for US efforts to round up vulnerable fissile materials and convert research reactors to low-enriched uranium.

Kramer, David

2014-05-01T23:59:59.000Z

326

E-Print Network 3.0 - arms reduction treaty Sample Search Results  

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

on fissile material security , the Comprehensive Test Ban Treaty , cooperative threat reduction, and others... Threat Reduction Agency , Fort Belvoir, Virginia Outline: 1....

327

Material-based design computation  

E-Print Network [OSTI]

The institutionalized separation between form, structure and material, deeply embedded in modernist design theory, paralleled by a methodological partitioning between modeling, analysis and fabrication, resulted in ...

Oxman, Neri

2010-01-01T23:59:59.000Z

328

MULTIDISCIPLINARY FREE MATERIAL OPTIMIZATION 1 ...  

E-Print Network [OSTI]

Nonlinear Anal. and Mech., Pitman, London, pages 136212, 1979. [22] R. Werner. Free Material Optimization. PhD thesis, Institute of Applied Mathematics II,...

2009-10-18T23:59:59.000Z

329

Vibrational Damping of Composite Materials  

E-Print Network [OSTI]

on the Damping of Composite Laminates, SPIE Proceedings onpublication to Journal of Composite Materials Biggerstaff,submitted for publication to Composites, Part A Biggerstaff,

Biggerstaff, Janet M.

2006-01-01T23:59:59.000Z

330

Toda Cathode Materials Production Facility  

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

Cathode Materials Production Facility 2013 DOE Vehicle Technologies Annual Merit Review May 13-17, 2013 David Han, Yasuhiro Abe Toda America Inc. Project ID: ARRAVT017...

331

Nanostructured Electrode Materials for Supercapacitors  

E-Print Network [OSTI]

and batteries/fuel cells. Nanostructured electrode materials have demonstrated superior electrochemical of polymethine dyes electronic spectra is crucial for successful design of the new molecules with optimized

Wu, Shin-Tson

332

Lightweighting Materials | Clean Energy | ORNL  

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

with lightweight materials can directly reduce fuel consump-tion. It also allows cars to carry advanced emissions control equipment, safety devices, and integrated...

333

Interim Management of Nuclear Materials  

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

containing dissolved nuclear materials and recovered isotopes in stainless-steel tanks; and product and scrap forms of metals or oxides in containers (cans, drums, etc.)...

334

NEBRASKA CENTER FOR MATERIALS AND NANOSCIENCE & CENTER FOR NANOHYBRID FUNCTIONAL MATERIALS  

E-Print Network [OSTI]

NEBRASKA CENTER FOR MATERIALS AND NANOSCIENCE & CENTER FOR NANOHYBRID FUNCTIONAL MATERIALS PRESENT FOR MATERIALS AND NANOSCIENCE & CENTER FOR NANOHYBRID FUNCTIONAL MATERIALS PRESENT Graphene Colloquium

Farritor, Shane

335

Materials and Methods Strain construction, materials, and Net1 mutagenesis  

E-Print Network [OSTI]

Materials and Methods Strain construction, materials, and Net1 mutagenesis All strains used and destruction boxes (Clb2C2DK100)HA3 was used in over-expression experiments with Clb2 (1). Net1 mutant constructs were created as previously described (2). Briefly, a wild type NET1-myc9 epitope tagged construct

Shou, Wenying

336

Material Safety Data Sheets | Department of Energy  

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

Material Safety Data Sheets Material Safety Data Sheets Material Safety Data Sheets (MSDSs) provide workers and emergency personnel with ways for handling and working with a...

337

Materials Sciences and Engineering Program | ORNL  

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

Materials Sciences and Engineering Program SHARE BES Materials Sciences and Engineering Program The ORNL materials sciences and engineering program supported by the Department of...

338

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

339

On the fracture toughness of advanced materials  

E-Print Network [OSTI]

toughness of advanced materials ?? By Maximilien E. LauneyAbstract: Few engineering materials are limited by theirare manufactured from materials that are comparatively low

Launey, Maximilien E.

2009-01-01T23:59:59.000Z

340

Cybersecurity Awareness Materials | Department of Energy  

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

Cybersecurity Awareness Materials Cybersecurity Awareness Materials The OCIO develops and distributes a variety of awareness material to be used during cyber awareness campaigns or...

Note: This page contains sample records for the topic "weapons-usable fissile materials" 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

Materials Theory, Modeling and Simulation | ORNL  

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

Materials Characterization Materials Theory and Simulation Quantum Monte Carlo Density Functional Theory Monte Carlo Ab Initio Molecular Dynamics Chemical and Materials Theory...

342

Disordered Materials Hold Promise for Better Batteries  

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

Disordered materials hold promise for better batteries Disordered Materials Hold Promise for Better Batteries February 21, 2014 | Tags: Chemistry, Hopper, Materials Science,...

343

Chemistry of Organic Electronic Materials 6483-Fall  

E-Print Network [OSTI]

Chemistry of Organic Electronic Materials 6483- Fall Tuesdays organic materials. The discussion will include aspects of synthesis General introduction to the electronic structure of organic materials with connection

Sherrill, David

344

Computational materials: Embedding Computation into the Everyday  

E-Print Network [OSTI]

Computational materials: Embedding Computation into thepaper presents research into material design merging thean integrated part of our material surroundings. Rather than

Thomsen, Mette Ramsgard; Karmon, Ayelet

2009-01-01T23:59:59.000Z

345

Chemical & Engineering Materials | More Science | ORNL  

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

Chemical & Engineering Materials SHARE Chemical and Engineering Materials Neutron-based research at SNS and HFIR in Chemical and Engineering Materials strives to understand the...

346

Sandia National Laboratories: Wavelength Conversion Materials  

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

TechnologiesWavelength Conversion Materials Wavelength Conversion Materials Overview of SSL Wavelength Conversion Materials Rare-Earth Phosphors Inorganic phosphors doped with...

347

Scientists produce transparent, light-harvesting material  

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

Transparent, light-harvesting material Scientists produce transparent, light-harvesting material The material could be used in development of transparent solar panels. November 3,...

348

Helpful links for materials transport, safety, etc.  

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

Helpful links for materials transport, safety, etc. relating to experiment safety at the APS. Internal Reference Material: Transporting Hazardous Materials "Natural" radioactivity...

349

Sandia National Laboratories: understanding of composite material...  

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

of composite material behavior in realistic wind applications Composite-Materials Fatigue Database Updated On January 22, 2014, in Energy, Materials Science, News, News & Events,...

350

PHASE TRANSFORMATIONS, STABILITY AND MATERIALS INTERACTIONS  

E-Print Network [OSTI]

mechanisms of turbine materials in this environment, whichTurbines Research Opportunities: Thermodynamics and kinetics of material-for designing improved materials. Gas turbines of the closed

Morris, Jr., J.W.

2010-01-01T23:59:59.000Z

351

Computational materials: Embedding Computation into the Everyday  

E-Print Network [OSTI]

building forces, smart materials are dynamic in that theymaterial With a smart material, we should be clearly1] Addington, M. 2001 Smart Materials and Technologies. In A

Thomsen, Mette Ramsgard; Karmon, Ayelet

2009-01-01T23:59:59.000Z

352

Sandia National Laboratories: Wavelength Conversion Materials  

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

EFRCOverviewWavelength Conversion Materials Wavelength Conversion Materials Overview of SSL Wavelength Conversion Materials Rare-Earth Phosphors Inorganic phosphors doped with...

353

Material selection for electrooptic deflectors  

SciTech Connect (OSTI)

The selection of a material for a practical device is generally guided by a number of criteria, including cost, size, difficulty of fabrication, durability, driver requirements, and system constraints. A quantitative analysis can usually be made for comparison, or a figure of merit can be computed. In the case of materials for electrooptical (EO) devices the choice is often made based on the availability of materials meeting some minimum system requirement. For fast EO deflectors, where a large number of resolvable spots is required, the choice of materials is quite limited. A model of just such a device is proposed; it is based on the resolution of 400 spots and reasonable boundary conditions. The model predicts that to be successful, an EO material must be chosen that has a linear EO coefficient (r/sub 33/) of at least 336 pm/V. A survey was conducted of the EO materials which are generally available. Based on the model and the survey, Czochralski crystal growth of strontium barium niobate (SBN:60) is recommended. Although SBN:60 does not have the largest EO coefficient, it may be the easiest to grow in the required size and optical quality, thus satisfying the availability criterion. It should be borne in mind that many materials may be grown by this technique and there are many new and potential applications for EO materials. 92 refs., 18 figs., 14 tabs.

Not Available

1988-09-01T23:59:59.000Z

354

Materials science Nanotubes get hard  

E-Print Network [OSTI]

Materials science Nanotubes get hard under pressure Proc. Natl Acad. Sci. USA doi:10.1073/pnas.0405877101 (2004) When Zhongwu Wang et al. squeezed carbon nanotubes in a diamond anvil cell, they made nanotubes into diamond itself: the carbon material formed under compression at room temperature seems

Downs, Robert T.

355

Creating Wave-Focusing Materials  

E-Print Network [OSTI]

Basic ideas for creating wave-focusing materials by injecting small particles in a given material are described. The number of small particles to be injected around any point is calculated. Inverse scattering problem with fixed wavenumber and fixed incident direction of the plane acoustic wave is formulated and solved.

A. G. Ramm

2008-05-16T23:59:59.000Z

356

Field of Expertise Materials Science  

E-Print Network [OSTI]

structure-property relationships through the characterisation of diverse materials to process optimisation and international research partners in order to keep Austrian high-technology industry, scientific production semiconductors Paper and physical chemistry principles of paper strength Metallic materials for energy applica

357

Material stabilization characterization management plan  

SciTech Connect (OSTI)

This document presents overall direction for characterization needs during stabilization of SNM at the Plutonium Finishing Plant (PFP). Technical issues for needed data and equipment are identified. Information on material categories and links to vulnerabilities are given. Comparison data on the material categories is discussed to assist in assessing the relative risks and desired processing priority.

GIBSON, M.W.

1999-08-31T23:59:59.000Z

358

Superconductivity and Magnetism: Materials Properties  

E-Print Network [OSTI]

.g. within high-Tc superconductivity, magnetic superconductors, MgB2, CMR materials, nanomagnetism and spin#12;#12;Superconductivity and Magnetism: Materials Properties and Developments #12;Copyright 2003 Risø National Laboratory Roskilde, Denmark ISBN 87-550-3244-3 ISSN 0907-0079 #12;Superconductivity

359

Nuclear Material Control and Accountability  

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

This Order establishes performance objectives, metrics, and requirements for developing, implementing, and maintaining a nuclear material control and accountability program within DOE/NNSA and for DOE-owned materials at other facilities that are exempt from licensing by the Nuclear Regulatory Commission. Cancels DOE M 470.4-6. Admin Chg 1, 8-3-11.

2011-06-27T23:59:59.000Z

360

Mercury-Related Materials Studies  

E-Print Network [OSTI]

. Pawel, "Assessment of Cavitation-Erosion Resistance of Potential Pump Impeller Materials for Mercury of Cavitation Resistant Modifications to Type 316LN Stainless Steel in a Mercury Thermal Convection Loop," OakMercury-Related Materials Studies Van Graves IDS NF Ph M tiIDS-NF Phone Meeting Jan 26, 2010

McDonald, Kirk

Note: This page contains sample records for the topic "weapons-usable fissile materials" 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

Mercury-Related Materials Studies  

E-Print Network [OSTI]

Mercury-Related Materials Studies Van Graves IDS NF Ph M tiIDS-NF Phone Meeting Jan 26, 2010 #12 Evaluation of Cavitation Resistance of Type 316LN Stainless Steel in Mercury Using a Vibratory Horn," J. Nucl Pump Impeller Materials for Mercury Service at the Spallation Neutron Source," Oak Ridge National

McDonald, Kirk

362

Radioactive Material Transportation Practices Manual  

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

This Manual establishes standard transportation practices for the Department of Energy, including National Nuclear Security Administration to use in planning and executing offsite shipments of radioactive materials and waste. The revision reflects ongoing collaboration of DOE and outside organizations on the transportation of radioactive material and waste. Cancels DOE M 460.2-1.

2008-06-04T23:59:59.000Z

363

Solar Thermal Reactor Materials Characterization  

SciTech Connect (OSTI)

Current research into hydrogen production through high temperature metal oxide water splitting cycles has created a need for robust high temperature materials. Such cycles are further enhanced by the use of concentrated solar energy as a power source. However, samples subjected to concentrated solar radiation exhibited lifetimes much shorter than expected. Characterization of the power and flux distributions representative of the High Flux Solar Furnace(HFSF) at the National Renewable Energy Laboratory(NREL) were compared to ray trace modeling of the facility. In addition, samples of candidate reactor materials were thermally cycled at the HFSF and tensile failure testing was performed to quantify material degradation. Thermal cycling tests have been completed on super alloy Haynes 214 samples and results indicate that maximum temperature plays a significant role in reduction of strength. The number of cycles was too small to establish long term failure trends for this material due to the high ductility of the material.

Lichty, P. R.; Scott, A. M.; Perkins, C. M.; Bingham, C.; Weimer, A. W.

2008-03-01T23:59:59.000Z

364

Radioactive waste material melter apparatus  

DOE Patents [OSTI]

An apparatus for preparing metallic radioactive waste material for storage is disclosed. The radioactive waste material is placed in a radiation shielded enclosure. The waste material is then melted with a plasma torch and cast into a plurality of successive horizontal layers in a mold to form a radioactive ingot in the shape of a spent nuclear fuel rod storage canister. The apparatus comprises a radiation shielded enclosure having an opening adapted for receiving a conventional transfer cask within which radioactive waste material is transferred to the apparatus. A plasma torch is mounted within the enclosure. A mold is also received within the enclosure for receiving the melted waste material and cooling it to form an ingot. The enclosure is preferably constructed in at least two parts to enable easy transport of the apparatus from one nuclear site to another.

Newman, Darrell F. (Richland, WA); Ross, Wayne A. (Richland, WA)

1990-01-01T23:59:59.000Z

365

Radioactive waste material melter apparatus  

DOE Patents [OSTI]

An apparatus for preparing metallic radioactive waste material for storage is disclosed. The radioactive waste material is placed in a radiation shielded enclosure. The waste material is then melted with a plasma torch and cast into a plurality of successive horizontal layers in a mold to form a radioactive ingot in the shape of a spent nuclear fuel rod storage canister. The apparatus comprises a radiation shielded enclosure having an opening adapted for receiving a conventional transfer cask within which radioactive waste material is transferred to the apparatus. A plasma torch is mounted within the enclosure. A mold is also received within the enclosure for receiving the melted waste material and cooling it to form an ingot. The enclosure is preferably constructed in at least two parts to enable easy transport of the apparatus from one nuclear site to another. 8 figs.

Newman, D.F.; Ross, W.A.

1990-04-24T23:59:59.000Z

366

Materials 1 Faculty of Engineering, Department of  

E-Print Network [OSTI]

Materials 1 Faculty of Engineering, Department of --Materials This publication refers syllabuses Materials The Department occupies newly refurbished premises over four floors of the Royal School and research in materials science and engineering, in particular nanomaterials, structural ceramics, theory

367

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.

368

Combinatorial Approaches for Hydrogen Storage Materials (presentation...  

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

Approaches for Hydrogen Storage Materials (presentation) Combinatorial Approaches for Hydrogen Storage Materials (presentation) Presentation on NIST Combinatorial Methods at the...

369

Webinar: Hydrogen Storage Materials Database Demonstration |...  

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

Storage Materials Database Demonstration Webinar: Hydrogen Storage Materials Database Demonstration Presentation slides from the Fuel Cell Technologies Office webinar "Hydrogen...

370

CHARACTERIZATION OF SIALON-TYPE MATERIALS  

E-Print Network [OSTI]

testing of ceramic materials. crucihle Thermal Shock Tests.and thermal shock. Among the various ceramic materials being

Spencer, P.N.

2010-01-01T23:59:59.000Z

371

Materials Technologies: Goals, Strategies, and Top Accomplishments...  

Energy Savers [EERE]

Materials Technologies: Goals, Strategies, and Top Accomplishments (Brochure), Vehicle Technologies Program (VTP) Materials Technologies: Goals, Strategies, and Top Accomplishments...

372

ITP Industrial Materials: Development and Commercialization of...  

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

Industrial Materials: Development and Commercialization of Alternative Carbon Fiber Precursors and Conversion Technologies ITP Industrial Materials: Development and...

373

Evaluation and Characterization of Lightweight Materials: Success...  

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

Characterization of Lightweight Materials: Success Stories from the High Temperature Materials Laboratory (HTML) User Program Evaluation and Characterization of Lightweight...

374

Materials Synthesis from Atoms to Systems | ORNL  

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

Porous Materials Thin Film Deposition Single Crystal Growth Texture Control Additive Manufacturing Nanomaterials Synthesis Designer Organic Molecules Related Research Materials...

375

Enhancing Railroad Hazardous Materials Transportation Safety...  

Office of Environmental Management (EM)

Enhancing Railroad Hazardous Materials Transportation Safety Rail Routing Enhancing Railroad Hazardous Materials Transportation Safety Rail Routing Presentation made by Kevin...

376

Engineering and Materials for Automotive Thermoelectric Applications...  

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

and Materials for Automotive Thermoelectric Applications Engineering and Materials for Automotive Thermoelectric Applications Design and optimization of TE exhaust generator,...

377

Catalyst material and method of making  

DOE Patents [OSTI]

The material of the present invention is a mixture of catalytically active material and carrier materials, which may be catalytically active themselves. Hence, the material of the present invention provides a catalyst particle that has catalytically active material throughout its bulk volume as well as on its surface. The presence of the catalytically active material throughout the bulk volume is achieved by chemical combination of catalytically active materials with carrier materials prior to or simultaneously with crystallite formation.

Matson, Dean W. (Kennewick, WA); Fulton, John L. (Richland, WA); Linehan, John C. (Richland, WA); Bean, Roger M. (Richland, WA); Brewer, Thomas D. (Richland, WA); Werpy, Todd A. (Richland, WA); Darab, John G. (Richland, WA)

1997-01-01T23:59:59.000Z

378

Recent Theoretical Results for Advanced Thermoelectric Materials...  

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

Materials Recent Theoretical Results for Advanced Thermoelectric Materials Transport theory and first principles calculations applied to oxides, chalcogenides and...

379

Proactive Strategies for Designing Thermoelectric Materials for...  

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

& Publications Proactive Strategies for Designing Thermoelectric Materials for Power Generation Proactive Strategies for Designing Thermoelectric Materials for Power Generation...

380

High Pressure Hydrogen Materials Compatibility of Piezoelectric...  

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

Pressure Hydrogen Materials Compatibility of Piezoelectric Films. High Pressure Hydrogen Materials Compatibility of Piezoelectric Films. Abstract: Abstract: Hydrogen is being...

Note: This page contains sample records for the topic "weapons-usable fissile materials" 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

Transformed materials : a material research center in Milan, Italy  

E-Print Network [OSTI]

[Transformed Materials] is an exploration into today's design methodologies of architecture production. The emergence of architectural form is questioned in relation to the temporal state of design intent and the physical ...

Skerry, Nathaniel S. (Nathaniel Standish), 1971-

2002-01-01T23:59:59.000Z

382

Storage depot for radioactive material  

DOE Patents [OSTI]

Vertical drilling of cylindrical holes in the soil, and the lining of such holes, provides storage vaults called caissons. A guarded depot is provided with a plurality of such caissons covered by shielded closures preventing radiation from penetrating through any linear gap to the atmosphere. The heat generated by the radioactive material is dissipated through the vertical liner of the well into the adjacent soil and thus to the ground surface so that most of the heat from the radioactive material is dissipated into the atmosphere in a manner involving no significant amount of biologically harmful radiation. The passive cooling of the radioactive material without reliance upon pumps, personnel, or other factor which might fail, constitutes one of the most advantageous features of this system. Moreover this system is resistant to damage from tornadoes or earthquakes. Hermetically sealed containers of radioactive material may be positioned in the caissons. Loading vehicles can travel throughout the depot to permit great flexibility of loading and unloading radioactive materials. Radioactive material can be shifted to a more closely spaced caisson after ageing sufficiently to generate much less heat. The quantity of material stored in a caisson is restricted by the average capacity for heat dissipation of the soil adjacent such caisson.

Szulinski, Milton J. (Richland, WA)

1983-01-01T23:59:59.000Z

383

Materials for solid state lighting  

SciTech Connect (OSTI)

Dramatic improvement in the efficiency of inorganic and organic light emitting diodes (LEDs and OLEDs) within the last decade has made these devices viable future energy efficient replacements for current light sources. However, both technologies must overcome major technical barriers, requiring significant advances in material science, before this goal can be achieved. Attention will be given to each technology associated with the following major areas of material research: (1) material synthesis, (2) process development, (3) device and defect physics, and (4) packaging. The discussion on material synthesis will emphasize the need for further development of component materials, including substrates and electrodes, necessary for improving device performance. The process technology associated with the LEDs and OLEDs is very different, but in both cases it is one factor limiting device performance. Improvements in process control and methodology are expected to lead to additional benefits of higher yield, greater reliability and lower costs. Since reliability and performance are critical to these devices, an understanding of the basic physics of the devices and device failure mechanisms is necessary to effectively improve the product. The discussion will highlight some of the more basic material science problems remaining to be solved. In addition, consideration will be given to packaging technology and the need for the development of novel materials and geometries to increase the efficiencies and reliability of the devices. The discussion will emphasize the performance criteria necessary to meet lighting applications, in order to illustrate the gap between current status and market expectations for future product.

Johnson, S.G.; Simmons, J.A.

2002-03-26T23:59:59.000Z

384

Materials Challenges in Nuclear Energy  

SciTech Connect (OSTI)

Nuclear power currently provides about 13% of the worldwide electrical power, and has emerged as a reliable baseload source of electricity. A number of materials challenges must be successfully resolved for nuclear energy to continue to make further improvements in reliability, safety and economics. The operating environment for materials in current and proposed future nuclear energy systems is summarized, along with a description of materials used for the main operating components. Materials challenges associated with power uprates and extensions of the operating lifetimes of reactors are described. The three major materials challenges for the current and next generation of water-cooled fission reactors are centered on two structural materials aging degradation issues (corrosion and stress corrosion cracking of structural materials and neutron-induced embrittlement of reactor pressure vessels), along with improved fuel system reliability and accident tolerance issues. The major corrosion and stress corrosion cracking degradation mechanisms for light water reactors are reviewed. The materials degradation issues for the Zr alloy clad UO2 fuel system currently utilized in the majority of commercial nuclear power plants is discussed for normal and off-normal operating conditions. Looking to proposed future (Generation IV) fission and fusion energy systems, there are 5 key bulk radiation degradation effects (low temperature radiation hardening and embrittlement, radiation-induced and modified solute segregation and phase stability, irradiation creep, void swelling, and high temperature helium embrittlement) and a multitude of corrosion and stress corrosion cracking effects (including irradiation-assisted phenomena) that can have a major impact on the performance of structural materials.

Zinkle, Steven J [ORNL] [ORNL; Was, Gary [University of Michigan] [University of Michigan

2013-01-01T23:59:59.000Z

385

Metal recovery from porous materials  

DOE Patents [OSTI]

A method for recovering plutonium and other metals from materials by leaching comprising the steps of incinerating the materials to form a porous matrix as the residue of incineration, immersing the matrix into acid in a microwave-transparent pressure vessel, sealing the pressure vessel, and applying microwaves so that the temperature and the pressure in the pressure vessel increase. The acid for recovering plutonium can be a mixture of HBF.sub.4 and HNO.sub.3 and preferably the pressure is increased to at least 100 PSI and the temperature to at least 200.degree. C. The porous material can be pulverized before immersion to further increase the leach rate.

Sturcken, Edward F. (P.O. Box 900, Isle of Palms, SC 29451)

1992-01-01T23:59:59.000Z

386

MSE 410: Materials Foundations for Energy Applications MSE 810: Materials for Energy Applications  

E-Print Network [OSTI]

; materials for future wind energy needs; thermoelectric materials for solid state energy conversion II: thermoelectric materials Introduction; the design of thermoelectric materials Morelli Jan 31, Feb 2 Module II: thermoelectric materials Thermal and electrical transport properties; model systems

387

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...

388

ATOMISTIC MODELING OF ELECTRODE MATERIALS  

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

life and rate * High cost of electrode materials * Project lead: Venkat Srinivasan (LBNL) * Marca Doeff (LBNL): Al-substituted layered Li-TM-O 2 * Phil Ross (LBNL) and Gerbrand...

389

Atomistic Modeling of Electrode Materials  

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

and rate * High cost of electrode materials * Project lead: John Newman * Marca Doeff (LBNL) on layered Li-TM-O 2 for effects of Al substitution * Phil Ross (LBNL) on nano-LiFePO...

390

Filter casting nanoscale porous materials  

DOE Patents [OSTI]

A method of producing nanoporous material includes the steps of providing a liquid, providing nanoparticles, producing a slurry of the liquid and the nanoparticles, removing the liquid from the slurry, and producing monolith.

Hayes, Joel Ryan; Nyce, Gregory Walker; Kuntz, Jushua David

2013-12-10T23:59:59.000Z

391

Energetic materials at extreme conditions  

E-Print Network [OSTI]

In order to effectively model the behaviour of energetic materials under operational conditions it is essential to obtain detailed structural information for these compounds at elevated temperature and/or pressures. The ...

Millar, David Iain Archibald

2011-06-27T23:59:59.000Z

392

Herty Advanced Materials Development Center  

Broader source: Energy.gov [DOE]

Session 1-B: Advancing Alternative Fuels for the Military and Aviation Sector Breakout Session 1: New Developments and Hot Topics Jill Stuckey, Acting Director, Herty Advanced Materials Development Center

393

SIDEWALL MATERIALS FOR ALUMINIUM SMELTER  

E-Print Network [OSTI]

SIDEWALL MATERIALS FOR ALUMINIUM SMELTER Reiza Zakia Mukhlis Supervisors: Dr. M. Akbar Rhamdhani heat losses *Grjotheim et al., 1988, Aluminium smelter technology #12;Reducing energy consumption anode cell* *Mukhlis, Rhamdhani and Brooks, TMS 2010 **Grjotheim et al., 1988, Aluminium smelter

Liley, David

394

Optimal Design of Heterogeneous Materials  

E-Print Network [OSTI]

are granular media, soils, polycrystals, sandstone, wood, bone, lungs, blood, animal and plant tissue, cell, electromagnetic, and mechanical properties of heterogeneous materials has a long and venerable history, attracting

Torquato, Salvatore

395

SHORT PROGRAMS Materials By Design  

E-Print Network [OSTI]

techniques including 3D printing, self-assembly, microfluidics and other technologies. We will distribute and analyze material samples designed based on multiscale simulations and manufactured using 3D printing

Entekhabi, Dara

396

Nuclear Material Control and Accountability  

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

The manual establishes a program for the control and accountability of nuclear materials within the Department of Energy. Cancels: DOE M 474.1-1B DOE M 474.1-2A

2005-08-26T23:59:59.000Z

397

Nuclear Material Control and Accountability  

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

The manual establishes a program for the control and accountability of nuclear materials within the Department of Energy. Chg 1, dated 8-14-06. Canceled by DOE O 474.2.

2005-08-26T23:59:59.000Z

398

Strategic raw material inventory optimization  

E-Print Network [OSTI]

The production of aerospace grade titanium alloys is concentrated in a relatively small number of producers. The market for these materials has always been cyclical in nature. During periods of high demand, metal producers ...

Vacha, Robin L. (Robin Lee)

2007-01-01T23:59:59.000Z

399

Momentive Performance Materials Distillation Intercharger  

E-Print Network [OSTI]

Presenter: Nicki (Collins) Boucher Project Team: T. Baisley, C. Beers, R. Cameron, K. Holman, T. Kotkoskie, K. Norris Momentive Performance Materials Inc. Waterford, NY May 23, 2013 Industrial Energy Technology Conference ACC Responsible... Care? Energy Efficiency Program Momentive Performance Materials Distillation Interchanger ESL-IE-13-05-20 Proceedings of the Thrity-Fifth Industrial Energy Technology Conference New Orleans, LA. May 21-24, 2013 Copyright 2013 Momentive Performance...

Boucher, N.; Baisley, T.; Beers, C.; Cameron, R.; Holman, K.; Kotkoskie, T.; Norris, K.

2013-01-01T23:59:59.000Z

400

Nondestructive ultrasonic testing of materials  

DOE Patents [OSTI]

Reflection wave forms obtained from aged and unaged material samples can be compared in order to indicate trends toward age-related flaws. Statistical comparison of a large number of data points from such wave forms can indicate changes in the microstructure of the material due to aging. The process is useful for predicting when flaws may occur in structural elements of high risk structures such as nuclear power plants, airplanes, and bridges.

Hildebrand, Bernard P. (Richland, WA)

1994-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "weapons-usable fissile materials" 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

Nuclear Material Control and Accountability  

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

This Order establishes performance objectives, metrics, and requirements for developing, implementing, and maintaining a nuclear material control and accountability program within DOE/NNSA and for DOE-owned materials at other facilities that are exempt from licensing by the Nuclear Regulatory Commission. Cancels DOE M 470.4-6, Admin Chg 1, 8-26-05. Admin Chg 2, dated 11-19-12, cancels DOE M 474.2 Admin Chg 1.

2011-06-27T23:59:59.000Z

402

Particle Suspension Mechanisms - Supplemental Material  

SciTech Connect (OSTI)

This supplemental material provides a brief introduction to particle suspension mechanisms that cause exfoliated skin cells to become and remain airborne. The material presented here provides additional context to the primary manuscript and serves as background for designing possible future studies to assess the impact of skin cells as a source of infectious aerosols. This introduction is not intended to be comprehensive and interested readers are encouraged to consult the references cited.

Dillon, M B

2011-03-03T23:59:59.000Z

403

Nanostructure material for supercapacitor application  

SciTech Connect (OSTI)

Transition metal nitrides and carbonitride materials were fabricated via sol-gel technology. The transition metal amides were synthesized by two methods: chemical route and electrolysis. The transition metal amides were then further polymerized, sintering to high temperature in an inert or reduced atmosphere. Transition metal nitrides and carbonitrides powders with surface area up to 160 m{sup 2}/g were obtained. The resultant electrode material showed high specific capacitance as crystalline ruthenium oxide.

Huang, Y.; Chu, C.T.; Wei, Q.; Zheng, H.

2000-07-01T23:59:59.000Z

404

Nondestructive ultrasonic testing of materials  

DOE Patents [OSTI]

Reflection wave forms obtained from aged and unaged material samples can be compared in order to indicate trends toward age-related flaws. Statistical comparison of a large number of data points from such wave forms can indicate changes in the microstructure of the material due to aging. The process is useful for predicting when flaws may occur in structural elements of high risk structures such as nuclear power plants, airplanes, and bridges. 4 figs.

Hildebrand, B.P.

1994-08-02T23:59:59.000Z

405

Methods for degrading lignocellulosic materials  

SciTech Connect (OSTI)

The present invention relates to methods for degrading a lignocellulosic material, comprising: treating the lignocellulosic material with an effective amount of one or more cellulolytic enzymes in the presence of at least one surfactant selected from the group consisting of a secondary alcohol ethoxylate, fatty alcohol ethoxylate, nonylphenol ethoxylate, tridecyl ethoxylate, and polyoxyethylene ether, wherein the presence of the surfactant increases the degradation of lignocellulosic material compared to the absence of the surfactant. The present invention also relates to methods for producing an organic substance, comprising: (a) saccharifying a lignocellulosic material with an effective amount of one or more cellulolytic enzymes in the presence of at least one surfactant selected from the group consisting of a secondary alcohol ethoxylate, fatty alcohol ethoxylate, nonylphenol ethoxylate, tridecyl ethoxylate, and polyoxyethylene ether, wherein the presence of the surfactant increases the degradation of lignocellulosic material compared to the absence of the surfactant; (b) fermenting the saccharified lignocellulosic material of step (a) with one or more fermenting microorganisms; and (c) recovering the organic substance from the fermentation.

Vlasenko, Elena (Davis, CA); Cherry, Joel (Davis, CA); Xu, Feng (Davis, CA)

2011-05-17T23:59:59.000Z

406

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

407

Radioactive material package seal tests  

SciTech Connect (OSTI)

General design or test performance requirements for radioactive materials (RAM) packages are specified in Title 10 of the US Code of Federal Regulations Part 71 (US Nuclear Regulatory Commission, 1983). The requirements for Type B packages provide a broad range of environments under which the system must contain the RAM without posing a threat to health or property. Seals that provide the containment system interface between the packaging body and the closure must function in both high- and low-temperature environments under dynamic and static conditions. A seal technology program, jointly funded by the US Department of Energy Office of Environmental Restoration and Waste Management (EM) and the Office of Civilian Radioactive Waste Management (OCRWM), was initiated at Sandia National Laboratories. Experiments were performed in this program to characterize the behavior of several static seal materials at low temperatures. Helium leak tests on face seals were used to compare the materials. Materials tested include butyl, neoprene, ethylene propylene, fluorosilicone, silicone, Eypel, Kalrez, Teflon, fluorocarbon, and Teflon/silicone composites. Because most elastomer O-ring applications are for hydraulic systems, manufacturer low-temperature ratings are based on methods that simulate this use. The seal materials tested in this program with a fixture similar to a RAM cask closure, with the exception of silicone S613-60, are not leak tight (1.0 {times} 10{sup {minus}7} std cm{sup 3}/s) at manufacturer low-temperature ratings. 8 refs., 3 figs., 1 tab.

Madsen, M.M.; Humphreys, D.L.; Edwards, K.R.

1990-01-01T23:59:59.000Z

408

Quantitative Characterization of Nanostructured Materials  

SciTech Connect (OSTI)

The two-and-a-half day symposium on the "Quantitative Characterization of Nanostructured Materials" will be the first comprehensive meeting on this topic held under the auspices of a major U.S. professional society. Spring MRS Meetings provide a natural venue for this symposium as they attract a broad audience of researchers that represents a cross-section of the state-of-the-art regarding synthesis, structure-property relations, and applications of nanostructured materials. Close interactions among the experts in local structure measurements and materials researchers will help both to identify measurement needs pertinent to ??real-world? materials problems and to familiarize the materials research community with the state-of-the-art local structure measurement techniques. We have chosen invited speakers that reflect the multidisciplinary and international nature of this topic and the need to continually nurture productive interfaces among university, government and industrial laboratories. The intent of the symposium is to provide an interdisciplinary forum for discussion and exchange of ideas on the recent progress in quantitative characterization of structural order in nanomaterials using different experimental techniques and theory. The symposium is expected to facilitate discussions on optimal approaches for determining atomic structure at the nanoscale using combined inputs from multiple measurement techniques.

Dr. Frank (Bud) Bridges, University of California-Santa Cruz

2010-08-05T23:59:59.000Z

409

Level 3 2013/14 Materials Engineering  

E-Print Network [OSTI]

Worsley EGA301 Composite Materials 10 Credits Dr. JC Arnold EG-353 Research Project 30 Credits Dr. CPLevel 3 2013/14 Materials Engineering BEng Materials Science and Engineering[J500,J502,J505] BEng Materials Science and Engineering with a year abroad[J510] MEng Materials Science and Engineering[J504] MEng

Harman, Neal.A.

410

Characterizing artificial electromagnetic materials and their hybridization with fundamentally resonant magnetic materials  

E-Print Network [OSTI]

4 Ferromagnetic Materials in Microstrip Structures . . . 4.1Ferromagnetic Materials . . . . . . . . . . . . . . 4.3 The1: positive material 1 , 1 > 0 . . . . . . . . . . . . . .

Gollub, Jonah Nathan

2008-01-01T23:59:59.000Z

411

Python Materials Genomics (pymatgen): A robust, open-source python library for materials analysis  

E-Print Network [OSTI]

Interface (API). As an example, using pymatgen's interface to the Materials Project's RESTful API materials data via the Materials Pro- ject's REpresentational State Transfer (REST) Application Programming

Southern California, University of

412

Displacement cascades in diatomic materials  

SciTech Connect (OSTI)

A new function, the specified-projectile displacement function p/sub ijk/ (E), is introduced to describe displacement cascades in polyatomic materials. This function describes the specific collision events that produce displacements and hence adds new information not previously available. Calculations of p/sub ijk/ (E) for MgO, Al/sub 2/O/sub 3/ and TaO are presented and discussed. Results show that the parameters that have the largest effect on displacement collision events are the PKA energy and the mass ratio of the atom types in the material. It is further shown that the microscopic nature of the displacement events changes over the entire recoil energy range relevant to fusion neutron spectra and that these changes are different in materials whose mass ratio is near one than in those where it is far from one.

Parkin, D.M.; Coulter, C.A.

1981-01-01T23:59:59.000Z

413

Metal recovery from porous materials  

DOE Patents [OSTI]

A method is described for recovering plutonium and other metals from materials by leaching comprising the steps of incinerating the materials to form a porous matrix as the residue of incineration, immersing the matrix into acid in a microwave-transparent pressure vessel, sealing the pressure vessel, and applying microwaves so that the temperature and the pressure in the pressure vessel increase. The acid for recovering plutonium can be a mixture of HBF[sub 4] and HNO[sub 3] and preferably the pressure is increased to at least 100 PSI and the temperature to at least 200 C. The porous material can be pulverized before immersion to further increase the leach rate.

Sturcken, E.F.

1992-10-13T23:59:59.000Z

414

Storage containers for radioactive material  

DOE Patents [OSTI]

A radioactive material storage system for use in the laboratory having a flat base plate with a groove in one surface thereof and a hollow pedestal extending perpendicularly away from the other surface thereof, a sealing gasket in the groove, a cover having a filter therein and an outwardly extending flange which fits over the plate, the groove and the gasket, and a clamp for maintaining the cover and the plate sealed together, whereby the plate and the cover and the clamp cooperate to provide a storage area for radioactive material readily accessible for use or

Groh, Edward F. (Naperville, IL); Cassidy, Dale A. (Valparaiso, IN); Dates, Leon R. (Elmwood Park, IL)

1981-01-01T23:59:59.000Z

415

Microrheological Characterisation of Anisotropic Materials  

E-Print Network [OSTI]

We describe the measurement of anisotropic viscoelastic moduli in complex soft materials, such as biopolymer gels, via video particle tracking microrheology of colloid tracer particles. The use of a correlation tensor to find the axes of maximum anisotropy, and hence the mechanical director, is described. The moduli of an aligned DNA gel are reported, as a test of the technique; this may have implications for high DNA concentrations in vivo. We also discuss the errors in microrheological measurement, and describe the use of frequency space filtering to improve displacement resolution, and hence probe these typically high modulus materials.

I A Hasnain; A M Donald

2006-03-03T23:59:59.000Z

416

Scintillator materials containing lanthanum fluorides  

DOE Patents [OSTI]

An improved radiation detector containing a crystalline mixture of LaF.sub.3 and CeF.sub.3 as the scintillator element is disclosed. Scintillators made with from 25% to 99.5% LaF.sub.3 and the remainder CeF.sub.3 have been found to provide a balance of good stopping power, high light yield and short decay constant that is equal to or superior to other known scintillator materials, and which may be processed from natural starting materials containing both rare earth elements. The radiation detectors disclosed are favorably suited for use in general purpose detection and in positron emission tomography.

Moses, William W. (Berkeley, CA)

1991-01-01T23:59:59.000Z

417

Scintillator materials containing lanthanum fluorides  

DOE Patents [OSTI]

An improved radiation detector containing a crystalline mixture of LaF[sub 3] and CeF[sub 3] as the scintillator element is disclosed. Scintillators made with from 25% to 99.5% LaF[sub 3] and the remainder CeF[sub 3] have been found to provide a balance of good stopping power, high light yield and short decay constant that is equal to or superior to other known scintillator materials, and which may be processed from natural starting materials containing both rare earth elements. The radiation detectors disclosed are favorably suited for use in general purpose detection and in positron emission tomography. 2 figures.

Moses, W.W.

1991-05-14T23:59:59.000Z

418

Storage containers for radioactive material  

DOE Patents [OSTI]

A radioactive material storage system is claimed for use in the laboratory having a flat base plate with a groove in one surface thereof and a hollow pedestal extending perpendicularly away from the other surface thereof, a sealing gasket in the groove, a cover having a filter therein and an outwardly extending flange which fits over the plate, the groove and the gasket, and a clamp for maintaining the cover and the plate sealed together. The plate and the cover and the clamp cooperate to provide a storage area for radioactive material readily accessible for use or inventory. Wall mounts are provided to prevent accidental formation of critical masses during storage.

Groh, E.F.; Cassidy, D.A.; Dates, L.R.

1980-07-31T23:59:59.000Z

419

Advanced Materials | More Science | ORNL  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth (AOD)ProductssondeadjustsondeadjustAbout the BuildingInnovation Portal Advanced MaterialMaterialsAdvanced

420

Towards an integrated materials characterization toolbox  

E-Print Network [OSTI]

The material characterization toolbox has recently experienced a number of parallel revolutionary advances, foreshadowing a time in the near future when material scientists can quantify material structure evolution across ...

Robertson, Ian M.

Note: This page contains sample records for the topic "weapons-usable fissile materials" 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

Magnetic spectroscopy and microscopy of functional materials  

E-Print Network [OSTI]

in the classical Heusler material Co 2 FeSi (Appendix B).plated self-assembly. Nature Materials, 3:823828, 2004.1 Concepts Functional materials are those with an industrial

Jenkins, C.A.

2012-01-01T23:59:59.000Z

422

MANUFACTURING ACCELERATING THE INCORPORATION OF MATERIALS  

E-Print Network [OSTI]

MANUFACTURING ACCELERATING THE INCORPORATION OF MATERIALS ADVANCES INTO MANUFACTURING PROCESSES NATIONAL NEED The proposed topic "Accelerating the Incorporation of Materials Advances into Manufacturing organizations, leading researchers from academic institutions, and others. Materials performance is often

Magee, Joseph W.

423

Tough, bio-inspired hybrid materials  

E-Print Network [OSTI]

S. Magonov, B. Ozturk, Nature Materials 2, 413 (Jun, L. J.Ager, R. O. Ritchie, Nature Materials 7, 672 (Aug, 2008). A.Guiden, Journal of Composite Materials D. R. Johnson, X. F.

Munch, Etienne

2009-01-01T23:59:59.000Z

424

Carbon-based Materials for Energy Storage  

E-Print Network [OSTI]

K. and Beguin, F. et. al Materials Science and Engineering BF. Advanced Functional Materials 17, 11, 1828-1836 (2007)and Silicone- Modified Materials ch7, 82-99 (2007) 3. Gdda,

Rice, Lynn Margaret

2012-01-01T23:59:59.000Z

425

CHARACTERIZATION OF SIALON-TYPE MATERIALS  

E-Print Network [OSTI]

an Economical Refractory Material", Industrial Heating, 50-of Sialon-Type Materials Newman Spencer Lawrence BerkeleyEXPERIHENTAL PROCEDURES A. The Material L Ml H2 M3 and M4 B.

Spencer, P.N.

2010-01-01T23:59:59.000Z

426

Systems and methods for treating material  

DOE Patents [OSTI]

Systems for treating material are provided that can include a vessel defining a volume, at least one conduit coupled to the vessel and in fluid communication with the vessel, material within the vessel, and NF.sub.3 material within the conduit. Methods for fluorinating material are provided that can include exposing the material to NF.sub.3 to fluorinate at least a portion of the material. Methods for separating components of material are also provided that can include exposing the material to NF.sub.3 to at least partially fluorinate a portion of the material, and separating at least one fluorinated component of the fluorinated portion from the material. The materials exposed to the NF.sub.3 material can include but are not limited to one or more of U, Ru, Rh, Mo, Tc, Np, Pu, Sb, Ag, Am, Sn, Zr, Cs, Th, and/or Rb.

Scheele, Randall D; McNamara, Bruce K

2014-10-21T23:59:59.000Z

427

Managing Research Materials and Data: Recordkeeping Guidelines  

E-Print Network [OSTI]

Managing Research Materials and Data: Recordkeeping Guidelines 1. Introduction Research Council and Universities Australia Managing Research Materials and Data: Recordkeeping Guidelines the management and disposal of research materials and data in accordance with the requirements

428

Combinatorial Approach for Hydrogen Storage Materials (presentation...  

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

Approach for Hydrogen Storage Materials (presentation) Combinatorial Approach for Hydrogen Storage Materials (presentation) Presented at the U.S. Department of Energy's Hydrogen...

429

Center for Lightweighting Automotive Materials and Processing...  

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

ti010mallick2011o.pdf More Documents & Publications Center for Lightweighting Automotive Materials and Processing Center for Lightweighting Automotive Materials and...

430

Center for Lightweighting Automotive Materials and Processing...  

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

D.C. ti06mallick.pdf More Documents & Publications Center for Lightweighting Automotive Materials and Processing Center for Lightweighting Automotive Materials and...

431

Sandia National Laboratories: Combining 'Tinkertoy' Materials...  

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

Materials with Solar Cells for Increased Photovoltaic Efficiency On December 4, 2014, in Energy, Materials Science, News, News & Events, Photovoltaic, Renewable Energy,...

432

Composite materials with integrated embedded sensing networks  

E-Print Network [OSTI]

Interlaminar Response of Composite Materials , ed. N. J.in fibre-reinforced composite structures with embedded fibreDutton, and D. Kelly. 2004. Composite Materials for Aircraft

Schaaf, Kristin Leigh

2008-01-01T23:59:59.000Z

433

Materials Characterization Capabilities at the High Temperature...  

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

2010 -- Washington D.C. lm028laracurzio2010o.pdf More Documents & Publications Materials Characterization Capabilities at the High Temperature Materials Laboratory and HTML...

434

Advanced Battery Materials Characterization: Success stories...  

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

Battery Materials Characterization: Success stories from the High Temperature Materials Laboratory (HTML) User Program Dr. E. Andrew Payzant, ORNL Project ID lmp02payzant This...

435

Materials Characterization Capabilities at the High Temperature...  

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

Review and Peer Evaluation lm028laracurzio2011o.pdf More Documents & Publications Materials Characterization Capabilities at the High Temperature Materials Laboratory and HTML...

436

Materials Characterization Capabilities at the High Temperature...  

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

and Peer Evaluation Meeting lm028laracurzio2012o.pdf More Documents & Publications Materials Characterization Capabilities at the High Temperature Materials Laboratory and HTML...

437

Advanced Thermoelectric Materials and Generator Technology for...  

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

Thermoelectric Materials and Generator Technology for Automotive Waste Heat at GM Advanced Thermoelectric Materials and Generator Technology for Automotive Waste Heat at GM...

438

Materials Selection Considerations for Thermal Process Equipment...  

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

Materials Selection Considerations for Thermal Process Equipment: A BestPractices Process Heating Technical Brief Materials Selection Considerations for Thermal Process Equipment:...

439

Advanced Materials for Proton Exchange Membranes | Department...  

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

Advanced Materials for Proton Exchange Membranes Advanced Materials for Proton Exchange Membranes A presentation to the High Temperature Membranes Working Group meeting, May 19,...

440

Lightweighting and Propulsion Materials Roadmapping Workshop...  

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

Lightweighting and Propulsion Materials Roadmapping Workshop Outbrief Lightweighting and Propulsion Materials Roadmapping Workshop Outbrief 2012 DOE Hydrogen and Fuel Cells Program...

Note: This page contains sample records for the topic "weapons-usable fissile materials" 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

Materials Characterization Capabilities at the High Temperature...  

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

May 18-22, 2009 -- Washington D.C. lm01laracurzio.pdf More Documents & Publications Materials Characterization Capabilities at the High Temperature Materials Laboratory and HTML...

442

High-Temperature Thermoelectric Materials Characterization for...  

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

High-Temperature Thermoelectric Materials Characterization for Automotive Waste Heat Recovery: Success Stories from the High Temperature Materials Laboratory (HTML) User Program...

443

ALS Ceramics Materials Research Advances Engine Performance  

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

ALS Ceramics Materials Research Advances Engine Performance ALS Ceramics Materials Research Advances Engine Performance Print Thursday, 27 September 2012 00:00 ritchie ceramics...

444

Materials Characterization Capabilities at the High Temperature...  

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

Laboratory: Focus on Carbon Fiber and Composites Materials Characterization Capabilities at the High Temperature Materials Laboratory: Focus on Carbon Fiber and Composites 2011 DOE...

445

Thermoelectric Bulk Materials from the Explosive Consolidation...  

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

Bulk Materials from the Explosive Consolidation of Nanopowders Thermoelectric Bulk Materials from the Explosive Consolidation of Nanopowders Describes technique of explosively...

446

High Temperature Thermoelectric Materials Characterization for...  

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

High Temperature Thermoelectric Materials Characterization for Automotive Waste Heat Recovery: Success Stories from the High Temperature Materials Laboratory (HTML) User Program...

447

Develop & evaluate materials & additives that enhance thermal...  

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

evaluate materials & additives that enhance thermal & overcharge abuse Develop & evaluate materials & additives that enhance thermal & overcharge abuse 2009 DOE Hydrogen Program...

448

Develop & Evaluate Materials & Additives that Enhance Thermal...  

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

Evaluate Materials & Additives that Enhance Thermal & Overcharge Abuse Develop & Evaluate Materials & Additives that Enhance Thermal & Overcharge Abuse 2011 DOE Hydrogen and Fuel...

449

Critical Materials Workshop Plenary Session Videos | Department...  

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

Critical Materials Workshop Plenary Session Videos Critical Materials Workshop Plenary Session Videos Welcome and Overview of Workshop and Energy Innovation Hubs Speakers * Dr. Leo...

450

Collaboration Shines in Materials Project Success  

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

Collaboration Shines in Materials Project Success Collaboration Shines in Materials Project Success Many Hands at Lab Lift 'World-Changing Idea' to New Heights December 12, 2013 |...

451

Waste Package Materials Performance Peer Review | Department...  

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

Waste Package Materials Performance Peer Review Waste Package Materials Performance Peer Review A consensus peer review of the current technical basis and the planned experimental...

452

Incorporating Copyrighted Material into STI Products | Scientific...  

Office of Scientific and Technical Information (OSTI)

Material into STI Products Print page Print page Most contractors have standard procedures that their researchers are not to include third-party copyrighted material within...

453

Free Material Optimization with Fundamental Eigenfrequency ...  

E-Print Network [OSTI]

The goal of this paper is to formulate and solve free material optimization ... Free material optimization (FMO) is a branch of structural optimization that gains in-.

2008-10-28T23:59:59.000Z

454

LOWER TEMPERATURE ELECTROLYTE AND ELECTRODE MATERIALS  

SciTech Connect (OSTI)

LSGM electrolyte and LSCF cathode materials were synthesized via solid state reaction and wet-chemical method. From these materials, symmetrical cells were fabricated for electrochemical characterizations.

Keqin Huang

2002-04-30T23:59:59.000Z

455

An Inexpensive Brazable Material for Magnetostrictive Sensors...  

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

More Like This Return to Search An Inexpensive Brazable Material for Magnetostrictive Sensors and Other Applications Based on Ferrite Materials Ames Laboratory Contact AMES About...

456

A MECHANICAL STRAIN SENSOR FOR POLYMERIC MATERIALS  

E-Print Network [OSTI]

A MECHANICAL STRAIN SENSOR FOR POLYMERIC MATERIALS AND PHOTOPHYSICAL INVESTIGATIONS OF LARGE ...................................................................................................... 17 A MECHANICAL STRAIN SENSOR FOR POLYMERIC MATERIALS ....... 21 3.1 Introduction

457

Scoping Materials | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Environmental Policy Act (NEPA) NEPA Reading Room SEIS for the Production of Tritium in a Commercial Light Water Reactor Scoping Materials Scoping Materials Scoping...

458

Magnesium Research in the Automotive Lightweighting Materials...  

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

in the Automotive Lightweighting Materials Program Magnesium Research in the Automotive Lightweighting Materials Program Presentation from the U.S. DOE Office of Vehicle...

459

Life Cycle Modeling of Propulsion Materials  

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

propulsion materials manufacturing technologies with an emphasis on aluminum, magnesium, titanium, and ceramics * Advanced propulsion materials' potential in heavy-duty...

460

Advances in understanding solar energy collection materials  

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

Understanding solar energy collection materials Advances in understanding solar energy collection materials A LANL team and collaborators have made advances in the understanding of...

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


461

Chemistry & Physics at Interfaces | Advanced Materials | ORNL  

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

Advanced Materials Home | Science & Discovery | Advanced Materials | Research Areas | Chemistry and Physics at Interfaces SHARE Chemistry and Physics at Interfaces Chemical...

462

CHARACTERIZATION OF SIALON-TYPE MATERIALS  

E-Print Network [OSTI]

is a candidate material for gas turbine engines. Ammann. atmaterials in large stationary power generation turbines --for better materials. the efficiency of gas turbines, by

Spencer, P.N.

2010-01-01T23:59:59.000Z

463

DOE and Critical Materials Video (Text Version)  

Broader source: Energy.gov [DOE]

This is a text version of the "DOE and Critical Materials" video presented at the Critical Materials Workshop, held on April 3, 2012 in Arlington, Virginia.

464

Proactive Strategies for Designing Thermoelectric Materials for...  

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

Proactive Strategies for Designing Thermoelectric Materials for Power Generation Proactive Strategies for Designing Thermoelectric Materials for Power Generation 2009 DOE Hydrogen...

465

Stability of Molten Core Materials  

SciTech Connect (OSTI)

The purpose of this report is to document a literature and data search for data and information pertaining to the stability of nuclear reactor molten core materials. This includes data and analysis from TMI-2 fuel and INLs LOFT (Loss of Fluid Test) reactor project and other sources.

Layne Pincock; Wendell Hintze

2013-01-01T23:59:59.000Z

466

Metal recovery from porous materials  

DOE Patents [OSTI]

The present invention relates to recovery of metals. More specifically, the present invention relates to the recovery of plutonium and other metals from porous materials using microwaves. The United States Government has rights in this invention pursuant to Contract No. DE-AC09-89SR18035 between the US Department of Energy and Westinghouse Savannah River Company.

Sturcken, E.F.

1991-01-01T23:59:59.000Z

467

Supporting Information Materials and Methods  

E-Print Network [OSTI]

1 Supporting Information Materials and Methods Description of Energy-Recycling Artificial Foot The energy-recycling artificial foot was comprised of six component groups: the attachment interface, the toe The prosthesis simulator boot weighed 1.30 kg, and the lift shoe weighed 1.42 kg, with each adding approximately

Collins, Steven H.

468

Separator material for electrochemical cells  

DOE Patents [OSTI]

An electrochemical cell is characterized as utilizing an aramid fiber as a separator material. The aramid fibers are especially suited for lithium/thionyl chloride battery systems. The battery separator made of aramid fibers possesses superior mechanical strength, chemical resistance, and is flame retardant.

Cieslak, W.R.; Storz, L.J.

1991-03-26T23:59:59.000Z

469

Material Stabilization Project Management Plan  

SciTech Connect (OSTI)

This plan presents the overall objectives, description, justification and planning for the plutonium Finishing Plant (PFP) Materials Stabilization project. The intent of this plan is to describe how this project will be managed and integrated with other facility stabilization and deactivation activities. This plan supplements the overall integrated plan presented in the Plutonium Finishing Plant Integrated Project Management Plan (IPMP), HNF-3617, Rev. 0. This is the top-level definitive project management document that specifies the technical (work scope), schedule, and cost baselines to manager the execution of this project. It describes the organizational approach and roles/responsibilities to be implemented to execute the project. This plan is under configuration management and any deviations must be authorized by appropriate change control action. Materials stabilization is designated the responsibility to open and stabilize containers of plutonium metal, oxides, alloys, compounds, and sources. Each of these items is at least 30 weight percent plutonium/uranium. The output of this project will be containers of materials in a safe and stable form suitable for storage pending final packaging and/or transportation offsite. The corrosion products along with oxides and compounds will be stabilized via muffle furnaces to reduce the materials to high fired oxides.

SPEER, D.R.

1999-09-01T23:59:59.000Z

470

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

471

Breakthrough materials for energy storage  

E-Print Network [OSTI]

Breakthrough materials for energy storage November 4, 2009 #12;#12;This revolution is happening;Electronics: our early market 5 hours #12;Progress on energy density... #12;Has reached a limit #12;Battery basics Anode Cathode #12;Battery basics Anode Cathode #12;Silicon leads in energy density

472

Separator material for electrochemical cells  

DOE Patents [OSTI]

An electrochemical cell characterized as utilizing an aramid fiber as a separator material. The aramid fibers are especially suited for lithium/thionyl chloride battery systems. The battery separator made of aramid fibers possesses superior mechanical strength, chemical resistance, and is flame retardant.

Cieslak, Wendy R. (1166 Laurel Loop NE., Albuquerque, NM 87122); Storz, Leonard J. (2215 Ambassador NE., Albuquerque, NM 87112)

1991-01-01T23:59:59.000Z

473

Process for preparing energetic materials  

DOE Patents [OSTI]

Sol-gel chemistry is used for the preparation of energetic materials (explosives, propellants and pyrotechnics) with improved homogeneity, and/or which can be cast to near-net shape, and/or made into precision molding powders. The sol-gel method is a synthetic chemical process where reactive monomers are mixed into a solution, polymerization occurs leading to a highly cross-linked three dimensional solid network resulting in a gel. The energetic materials can be incorporated during the formation of the solution or during the gel stage of the process. The composition, pore, and primary particle sizes, gel time, surface areas, and density may be tailored and controlled by the solution chemistry. The gel is then dried using supercritical extraction to produce a highly porous low density aerogel or by controlled slow evaporation to produce a xerogel. Applying stress during the extraction phase can result in high density materials. Thus, the sol-gel method can be used for precision detonator explosive manufacturing as well as producing precision explosives, propellants, and pyrotechnics, along with high power composite energetic materials.

Simpson, Randall L. (Livermore, CA); Lee, Ronald S. (Livermore, CA); Tillotson, Thomas M. (Tracy, CA; , Hrubesh, Lawrence W. (Pleasanton, CA); Swansiger, Rosalind W. (Livermore, CA); Fox, Glenn A. (Livermore, CA)

2011-12-13T23:59:59.000Z

474

Progress in Fusion Materials Research  

E-Print Network [OSTI]

reactors Qualification requires all of the mechanical property testing on unirradiated material, plus. Koizumi et al., Proc. Int. Gas Turbines Conf., 2003, paper TS-119 #12;6 Managed by UT-Battelle for the U is strongly dependent on annealing conditions FHR: fast heating rate (>1000C/min) SFR: slow heating rate (10

475

Department of Advanced Materials Science  

E-Print Network [OSTI]

device, Bioconjugate matsuura@k.u-tokyo.ac.jpe-mail 04-7136-3781T E L Environmental-friendly materials Nuclear magnetic resonance, Quantum spin systems, Low temperature physics, Strongly correlated electron Effect takatama@spring8.or.jpe-mail 0791-58-2942T E L Synchrotron Radiation, X-ray Free Electron Laser

Katsumoto, Shingo

476

Durability of Materials in a Stress-Response Framework: Acrylic Materials for Photovoltaic Systems  

E-Print Network [OSTI]

Durability of Materials in a Stress-Response Framework: Acrylic Materials for Photovoltaic Systems materials for enhanced photovoltaic (PV) performance, it is critical to have quantitative knowledge developed for solar radiation durability studies of solar and environmentally exposed photovoltaic materials

Rollins, Andrew M.

477

Materials Characterization Capabilities at the High Temperature Materials  

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 ofMaterialLaboratory and

478

Materials Characterization Capabilities at the High Temperature Materials  

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 ofMaterialLaboratory

479

Armor systems including coated core materials  

DOE Patents [OSTI]

An armor system and method involves providing a core material and a stream of atomized coating material that comprises a liquid fraction and a solid fraction. An initial layer is deposited on the core material by positioning the core material in the stream of atomized coating material wherein the solid fraction of the stream of atomized coating material is less than the liquid fraction of the stream of atomized coating material on a weight basis. An outer layer is then deposited on the initial layer by positioning the core material in the stream of atomized coating material wherein the solid fraction of the stream of atomized coating material is greater than the liquid fraction of the stream of atomized coating material on a weight basis.

Chu, Henry S. (Idaho Falls, ID); Lillo, Thomas M. (Idaho Falls, ID); McHugh, Kevin M. (Idaho Falls, ID)

2012-07-31T23:59:59.000Z

480

Armor systems including coated core materials  

DOE Patents [OSTI]

An armor system and method involves providing a core material and a stream of atomized coating material that comprises a liquid fraction and a solid fraction. An initial layer is deposited on the core material by positioning the core material in the stream of atomized coating material wherein the solid fraction of the stream of atomized coating material is less than the liquid fraction of the stream of atomized coating material on a weight basis. An outer layer is then deposited on the initial layer by positioning the core material in the stream of atomized coating material wherein the solid fraction of the stream of atomized coating material is greater than the liquid fraction of the stream of atomized coating material on a weight basis.

2013-10-08T23:59:59.000Z

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


481

Systems and methods for forming defects on graphitic materials and curing radiation-damaged graphitic materials  

DOE Patents [OSTI]

Systems and methods are disclosed herein for forming defects on graphitic materials. The methods for forming defects include applying a radiation reactive material on a graphitic material, irradiating the applied radiation reactive material to produce a reactive species, and permitting the reactive species to react with the graphitic material to form defects. Additionally, disclosed are methods for removing defects on graphitic materials.

Ryu, Sunmin; Brus, Louis E.; Steigerwald, Michael L.; Liu, Haitao

2012-09-25T23:59:59.000Z

482

Hydrocarbon sensors and materials therefor  

DOE Patents [OSTI]

An electrochemical hydrocarbon sensor and materials for use in sensors. A suitable proton conducting electrolyte and catalytic materials have been found for specific application in the detection and measurement of non-methane hydrocarbons. The sensor comprises a proton conducting electrolyte sandwiched between two electrodes. At least one of the electrodes is covered with a hydrocarbon decomposition catalyst. Two different modes of operation for the hydrocarbon sensors can be used: equilibrium versus non-equilibrium measurements and differential catalytic. The sensor has particular application for on-board monitoring of automobile exhaust gases to evaluate the performance of catalytic converters. In addition, the sensor can be utilized in monitoring any process where hydrocarbons are exhausted, for instance, industrial power plants. The sensor is low cost, rugged, sensitive, simple to fabricate, miniature, and does not suffer cross sensitivities.

Pham, Ai Quoc (San Jose, CA); Glass, Robert S. (Livermore, CA)

2000-01-01T23:59:59.000Z

483

Polymer electronic devices and materials.  

SciTech Connect (OSTI)

Polymer electronic devices and materials have vast potential for future microsystems and could have many advantages over conventional inorganic semiconductor based systems, including ease of manufacturing, cost, weight, flexibility, and the ability to integrate a wide variety of functions on a single platform. Starting materials and substrates are relatively inexpensive and amenable to mass manufacturing methods. This project attempted to plant the seeds for a new core competency in polymer electronics at Sandia National Laboratories. As part of this effort a wide variety of polymer components and devices, ranging from simple resistors to infrared sensitive devices, were fabricated and characterized. Ink jet printing capabilities were established. In addition to promising results on prototype devices the project highlighted the directions where future investments must be made to establish a viable polymer electronics competency.

Schubert, William Kent; Baca, Paul Martin; Dirk, Shawn M.; Anderson, G. Ronald; Wheeler, David Roger

2006-01-01T23:59:59.000Z

484

Special nuclear material simulation device  

DOE Patents [OSTI]

An apparatus for simulating special nuclear material is provided. The apparatus typically contains a small quantity of special nuclear material (SNM) in a configuration that simulates a much larger quantity of SNM. Generally the apparatus includes a spherical shell that is formed from an alloy containing a small quantity of highly enriched uranium. Also typically provided is a core of depleted uranium. A spacer, typically aluminum, may be used to separate the depleted uranium from the shell of uranium alloy. A cladding, typically made of titanium, is provided to seal the source. Methods are provided to simulate SNM for testing radiation monitoring portals. Typically the methods use at least one primary SNM spectral line and exclude at least one secondary SNM spectral line.

Leckey, John H.; DeMint, Amy; Gooch, Jack; Hawk, Todd; Pickett, Chris A.; Blessinger, Chris; York, Robbie L.

2014-08-12T23:59:59.000Z

485

CONTAINER MATERIALS, FABRICATION AND ROBUSTNESS  

SciTech Connect (OSTI)

The multi-barrier 3013 container used to package plutonium-bearing materials is robust and thereby highly resistant to identified degradation modes that might cause failure. The only viable degradation mechanisms identified by a panel of technical experts were pressurization within and corrosion of the containers. Evaluations of the container materials and the fabrication processes and resulting residual stresses suggest that the multi-layered containers will mitigate the potential for degradation of the outer container and prevent the release of the container contents to the environment. Additionally, the ongoing surveillance programs and laboratory studies should detect any incipient degradation of containers in the 3013 storage inventory before an outer container is compromised.

Dunn, K.; Louthan, M.; Rawls, G.; Sindelar, R.; Zapp, P.; Mcclard, J.

2009-11-10T23:59:59.000Z

486

High temperature structural insulating material  

DOE Patents [OSTI]

A high temperature structural insulating material useful as a liner for cylinders of high temperature engines through the favorable combination of high service temperature (above about 800/sup 0/C), low thermal conductivity (below about 0.2 W/m/sup 0/C), and high compressive strength (above about 250 psi). The insulating material is produced by selecting hollow ceramic beads with a softening temperature above about 800/sup 0/C, a diameter within the range of 20-200 ..mu..m, and a wall thickness in the range of about 2 to 4 ..mu..m; compacting the beads and a compatible silicate binder composition under pressure and sintering conditions to provide the desired structural form with the structure having a closed-cell, compact array of bonded beads.

Chen, W.Y.

1984-07-27T23:59:59.000Z

487

High temperature structural insulating material  

DOE Patents [OSTI]

A high temperature structural insulating material useful as a liner for cylinders of high temperature engines through the favorable combination of high service temperature (above about 800.degree. C.), low thermal conductivity (below about 0.2 W/m.degree. C.), and high compressive strength (above about 250 psi). The insulating material is produced by selecting hollow ceramic beads with a softening temperature above about 800.degree. C., a diameter within the range of 20-200 .mu.m, and a wall thickness in the range of about 2-4 .mu.m; compacting the beads and a compatible silicate binder composition under pressure and sintering conditions to provide the desired structural form with the structure having a closed-cell, compact array of bonded beads.

Chen, Wayne Y. (Munster, IN)

1987-01-01T23:59:59.000Z

488

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

489

Enabling Informed Adaptation of Reformed Instructional Materials  

E-Print Network [OSTI]

Enabling Informed Adaptation of Reformed Instructional Materials Rachel E. Scherr and Andrew Elby 20742 USA Abstract. Instructors inevitably need to adapt even the best reform materials to suit instructors, and video clips of students working on the materials. Our materials thus facilitate their own

Elby, Andy

490

Recycled Materials Resource Jeffrey S. Melton  

E-Print Network [OSTI]

Recycled Materials Resource Center Jeffrey S. Melton Outreach Director Recycled Materials Resource Center NCC Meeting, April 9th, 2008 #12;Recycled Materials Resource Center Partner laboratory of FHWA Founded in 1998, renewed in 2007 Dedicated to the appropriate use of recycled materials in the highway

491

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

492

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

493

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

494

Carbon-based Materials for Energy Storage  

E-Print Network [OSTI]

China National Program (2011CB932602) and the Center for Molecularly Assembled Material Architectures for Solar

Rice, Lynn Margaret

2012-01-01T23:59:59.000Z

495

Nanocomposite of graphene and metal oxide materials  

DOE Patents [OSTI]

Nanocomposite materials comprising a metal oxide bonded to at least one graphene material. The nanocomposite materials exhibit a specific capacity of at least twice that of the metal oxide material without the graphene at a charge/discharge rate greater than about 10C.

Liu, Jun; Aksay, Ilhan A.; Choi, Daiwon; Wang, Donghai; Yang, Zhenguo

2012-09-04T23:59:59.000Z

496

CALCULATING OPTICAL CONSTANTS OF GLAZING MATERIALS  

E-Print Network [OSTI]

Solar Energy CALCULATING OPTICAL CONSTANTS OF GLAZING MATERIALS Michael Rub August 1981 TWO-WEEK LOAN

Rubin, Michael

2013-01-01T23:59:59.000Z

497

Encapsulant materials and associated devices  

DOE Patents [OSTI]

Compositions suitable for use as encapsulants are described. The inventive compositions include a high molecular weight polymeric material, a curing agent, an inorganic compound, and a coupling agent. Optional elements include adhesion promoting agents, colorants, antioxidants, and UV absorbers. The compositions have desirable diffusivity properties, making them suitable for use in devices in which a substantial blocking of moisture ingress is desired, such as photovoltaic (PV) modules.

Kempe, Michael D (Littleton, CO); Thapa, Prem (Lima, OH)

2012-05-22T23:59:59.000Z

498

Encapsulant materials and associated devices  

DOE Patents [OSTI]

Compositions suitable for use as encapsulants are described. The inventive compositions include a high molecular weight polymeric material, a curing agent, an inorganic compound, and a coupling agent. Optional elements include adhesion promoting agents, colorants, antioxidants, and UV absorbers. The compositions have desirable diffusivity properties, making them suitable for use in devices in which a substantial blocking of moisture ingress is desired, such as photovoltaic (PV) modules.

Kempe, Michael D (Littleton, CO); Thapa, Prem (Lima, OH)

2011-03-08T23:59:59.000Z

499

Method of sintering ceramic materials  

DOE Patents [OSTI]

A method for sintering ceramic materials is described. A ceramic article is coated with layers of protective coatings such as boron nitride, graphite foil, and niobium. The coated ceramic article is embedded in a container containing refractory metal oxide granules and placed within a microwave oven. The ceramic article is heated by microwave energy to a temperature sufficient to sinter the ceramic article to form a densified ceramic article having a density equal to or greater than 90% of theoretical density. 2 figs.

Holcombe, C.E.; Dykes, N.L.

1992-11-17T23:59:59.000Z

500

Dense, finely, grained composite materials  

DOE Patents [OSTI]

Dense, finely grained composite materials comprising one or more ceramic phase or phase and one or more metallic and/or intermetallic phase or phases are produced by combustion synthesis. Spherical ceramic grains are homogeneously dispersed within the matrix. Methods are provided, which include the step of applying mechanical pressure during or immediately after ignition, by which the microstructures in the resulting composites can be controllably selected.

Dunmead, Stephen D. (Davis, CA); Holt, Joseph B. (San Jose, CA); Kingman, Donald D. (Danville, CA); Munir, Zuhair A. (Davis, CA)

1990-01-01T23:59:59.000Z