National Library of Energy BETA

Sample records for method specific criteria

  1. Evolving treatment plan quality criteria from institution-specific experience

    SciTech Connect (OSTI)

    Ruan, D.; Shao, W.; DeMarco, J.; Tenn, S.; King, C.; Low, D.; Kupelian, P.; Steinberg, M.

    2012-05-15

    Purpose: The dosimetric aspects of radiation therapy treatment plan quality are usually evaluated and reported with dose volume histogram (DVH) endpoints. For clinical practicality, a small number of representative quantities derived from the DVH are often used as dose endpoints to summarize the plan quality. National guidelines on reference values for such quantities for some standard treatment approaches are often used as acceptance criteria to trigger treatment plan review. On the other hand, treatment prescription and planning approaches specific to each institution warrants the need to report plan quality in terms of practice consistency and with respect to institution-specific experience. The purpose of this study is to investigate and develop a systematic approach to record and characterize the institution-specific plan experience and use such information to guide the design of plan quality criteria. In the clinical setting, this approach will assist in (1) improving overall plan quality and consistency and (2) detecting abnormal plan behavior for retrospective analysis. Methods: The authors propose a self-evolving methodology and have developed an in-house prototype software suite that (1) extracts the dose endpoints from a treatment plan and evaluates them against both national standard and institution-specific criteria and (2) evolves the statistics for the dose endpoints and updates institution-specific criteria. Results: The validity of the proposed methodology was demonstrated with a database of prostate stereotactic body radiotherapy cases. As more data sets are accumulated, the evolving institution-specific criteria can serve as a reliable and stable consistency measure for plan quality and reveals the potential use of the ''tighter'' criteria than national standards or projected criteria, leading to practice that may push to shrink the gap between plans deemed acceptable and the underlying unknown optimality. Conclusions: The authors have developed

  2. End Points Specification Methods

    Office of Energy Efficiency and Renewable Energy (EERE)

    Two methods to develop end point specifications are presented. These have evolved from use in the field for deactivation projects.

  3. Falcon: automated optimization method for arbitrary assessment criteria

    DOE Patents [OSTI]

    Yang, Tser-Yuan; Moses, Edward I.; Hartmann-Siantar, Christine

    2001-01-01

    FALCON is a method for automatic multivariable optimization for arbitrary assessment criteria that can be applied to numerous fields where outcome simulation is combined with optimization and assessment criteria. A specific implementation of FALCON is for automatic radiation therapy treatment planning. In this application, FALCON implements dose calculations into the planning process and optimizes available beam delivery modifier parameters to determine the treatment plan that best meets clinical decision-making criteria. FALCON is described in the context of the optimization of external-beam radiation therapy and intensity modulated radiation therapy (IMRT), but the concepts could also be applied to internal (brachytherapy) radiotherapy. The radiation beams could consist of photons or any charged or uncharged particles. The concept of optimizing source distributions can be applied to complex radiography (e.g. flash x-ray or proton) to improve the imaging capabilities of facilities proposed for science-based stockpile stewardship.

  4. END POINTS SPECIFICATION METHODS End Points Specification Methods

    Office of Environmental Management (EM)

    SPECIFICATION METHODS End Points Specification Methods Hierarchical End-Points Method Checklist End-Points Method Two methods to develop end point specifications are presented. These have evolved from use in the field for deactivation projects.  The hierarchical method is systematic, comprehensive, and completely defensible as to the basis for each specification. This method may appear complex to the uninitiated, but it is a straightforward application of a systematic engineering approach. It

  5. Methods and criteria for safety analysis (FIN L2535)

    SciTech Connect (OSTI)

    Not Available

    1992-12-01

    In response to the NRC request for a proposal dated October 20, 1992, Westinghouse Savannah River Company (WSRC) submit this proposal to provide contractural assistance for FIN L2535, ``Methods and Criteria for Safety Analysis,`` as specified in the Statement of Work attached to the request for proposal. The Statement of Work involves development of safety analysis guidance for NRC licensees, arranging a workshop on this guidance, and revising NRC Regulatory Guide 3.52. This response to the request for proposal offers for consideration the following advantages of WSRC in performing this work: Experience, Qualification of Personnel and Resource Commitment, Technical and Organizational Approach, Mobilization Plan, Key Personnel and Resumes. In addition, attached are the following items required by the NRC: Schedule II, Savannah River Site - Job Cost Estimate, NRC Form 189, Project and Budget Proposal for NRC Work, page 1, NRC Form 189, Project and Budget Proposal for NRC Work, page 2, Project Description.

  6. Proposed GTA welding specification and acceptance criteria for the MC4163

    SciTech Connect (OSTI)

    Kwiatkowski, J.J.

    1991-04-12

    This specification documents the gas tungsten arc (GTA) welding process and production weld acceptance criteria requirements for the MC4163. This document is written specifically to apply to the welds on the MC4163 and is not to be used as a general gas tungsten arc welding specification. All sections of this specification must be complied with unless specifically exempted in writing. There are a total of five welds with three different joint designs required to fabricate the MC4163. In the order of fabrication they are (1) initiator closure disc, (2) nozzle to case girth welds, two and, (3) nozzle closure disc welds, two. This specification will only address the nozzle to case girth welds and the nozzle closure disc welds.

  7. Methods for chromosome-specific staining

    DOE Patents [OSTI]

    Gray, Joe W.; Pinkel, Daniel

    1995-01-01

    Methods and compositions for chromosome-specific staining are provided. Compositions comprise heterogenous mixtures of labeled nucleic acid fragments having substantially complementary base sequences to unique sequence regions of the chromosomal DNA for which their associated staining reagent is specific. Methods include methods for making the chromosome-specific staining compositions of the invention, and methods for applying the staining compositions to chromosomes.

  8. Methods for chromosome-specific staining

    DOE Patents [OSTI]

    Gray, J.W.; Pinkel, D.

    1995-09-05

    Methods and compositions for chromosome-specific staining are provided. Compositions comprise heterogeneous mixtures of labeled nucleic acid fragments having substantially complementary base sequences to unique sequence regions of the chromosomal DNA for which their associated staining reagent is specific. Methods include ways for making the chromosome-specific staining compositions of the invention, and methods for applying the staining compositions to chromosomes. 3 figs.

  9. Methods for verifying compliance with low-level radioactive waste acceptance criteria

    SciTech Connect (OSTI)

    NONE

    1993-09-01

    This report summarizes the methods that are currently employed and those that can be used to verify compliance with low-level radioactive waste (LLW) disposal facility waste acceptance criteria (WAC). This report presents the applicable regulations representing the Federal, State, and site-specific criteria for accepting LLW. Typical LLW generators are summarized, along with descriptions of their waste streams and final waste forms. General procedures and methods used by the LLW generators to verify compliance with the disposal facility WAC are presented. The report was written to provide an understanding of how a regulator could verify compliance with a LLW disposal facility`s WAC. A comprehensive study of the methodology used to verify waste generator compliance with the disposal facility WAC is presented in this report. The study involved compiling the relevant regulations to define the WAC, reviewing regulatory agency inspection programs, and summarizing waste verification technology and equipment. The results of the study indicate that waste generators conduct verification programs that include packaging, classification, characterization, and stabilization elements. The current LLW disposal facilities perform waste verification steps on incoming shipments. A model inspection and verification program, which includes an emphasis on the generator`s waste application documentation of their waste verification program, is recommended. The disposal facility verification procedures primarily involve the use of portable radiological survey instrumentation. The actual verification of generator compliance to the LLW disposal facility WAC is performed through a combination of incoming shipment checks and generator site audits.

  10. Determining site-specific drum loading criteria for storing combustible {sup 238}Pu waste

    SciTech Connect (OSTI)

    Marshall, R.S.; Callis, E.L.; Cappis, J.H.; Espinoza, J.M.; Foltyn, E.M.; Reich, B.T.; Smith, M.C.

    1994-02-01

    Waste containing hydrogenous-combustible material contaminated with {sup 238}Pu can generate hydrogen gas at appreciable rates through alpha radiolysis. To ensure safe transportation of WIPP drums, the limit for {sup 238}Pu-combustible waste published in the WIPP TRUPACT-11 CONTENT (TRUCON) CODES is 21 milliwafts per 55 gallon drum. This corresponds to about 45 milligrams of {sup 238}PuO{sub 2} used for satellite heat source-electrical generators. The Los Alamos waste storage site adopted a {sup 238}Pu waste storage criteria based on these TRCUCON codes. However, reviews of the content in drums of combustible waste generated during heat source assembly at Los Alamos showed the amount of {sup 238}Pu is typically much greater than 45 milligrams. It is not feasible to appreciably reduce Los Alamos {sup 238}Pu waste drum loadings without significantly increasing waste volumes or introducing unsafe practices. To address this concern, a series of studies were implemented to evaluate the applicability of the TRUCON limits for storage of this specific waste. Addressed in these evaluations were determination of the hydrogen generation rate, hydrogen diffusion rates through confinement layers and vent filters, and packaging requirements specific to Los Alamos generated {sup 238}Pu contaminated combustible waste. These studies also showed that the multiple-layer packaging practices in use at Los Alamos could be relaxed without significantly increasing the risk of contamination. Based on a model developed to predict H{sub 2} concentrations in packages and drum headspace, the site specific effective hydrogen generation rate, and hydrogen-diffusion values, and revising the waste packaging practices, we were able to raise the safe loading limit for {sup 238}Pu waste drums for on site storage to the gram levels typical of currently generated {sup 238}Pu waste.

  11. Individual-specific antibody identification methods

    DOE Patents [OSTI]

    Francoeur, Ann -Michele

    1989-11-14

    An identification method, applicable to the identification of animals or inanimate objects, is described. The method takes advantage of a hithertofore unknown set of individual-specific, or IS antibodies, that are part of the unique antibody repertoire present in animals, by reacting an effective amount of IS antibodies with a particular panel, or n-dimensional array (where n is typically one or two) consisting of an effective amount of many different antigens (typically greater than one thousand), to give antibody-antigen complexes. The profile or pattern formed by the antigen-antibody complexes, termed an antibody fingerprint, when revealed by an effective amount of an appropriate detector molecule, is uniquely representative of a particular individual. The method can similarly by used to distinguish genetically, or otherwise similar individuals, or their body parts containing IS antibodies. Identification of inanimate objects, particularly security documents, is similarly affected by associating with the documents, an effective amount of a particular individual's IS antibodies, or conversely, a particular panel of antigens, and forming antibody-antigen complexes with a particular panel of antigens, or a particular individual's IS antibodies, respectively. One embodiment of the instant identification method, termed the blocked fingerprint assay, has applications in the area of allergy testing, autoimmune diagnostics and therapeutics, and the detection of environmental antigens such as pathogens, chemicals, and toxins.

  12. Site Specific Metal Criteria Developed Using Kentucky Division of Water Procedures

    SciTech Connect (OSTI)

    Kszos, L.A.; Phipps, T.L.

    1999-10-09

    Alternative limits for Cu, Ni, Pb, and Zn were developed for treated wastewater from four outfalls at a Gaseous Diffusion Plant. Guidance from the Kentucky Division of Water (KDOW) was used to (1) estimate the toxicity of the effluents using water fleas (Ceriodaphnia dubia) and fathead minnow (Pimephales promelas) larvae; (2) determine total recoverable and dissolved concentrations of Cu, Pb, Ni, and Zn ; (3) calculate ratios of dissolved metal (DM) to total recoverable metal (TRM); and (4) assess chemical characteristics of the effluents. Three effluent samples from each outfall were collected during each of six test periods; thus, a total of 18 samples from each outfall were evaluated for toxicity, DM and TRM. Subsamples were analyzed for alkalinity, hardness, pH, conductivity, and total suspended solids. Short-term (6 or 7 d), static renewal toxicity tests were conducted according to EPA methodology. Ceriodaphnia reproduction was reduced in one test of effluent from Outfall A , and effluent from Outfall B was acutely toxic to both test species during one test. However, the toxicity was not related to the metals present in the effluents. Of the 18 samples from each outfall, more than 65% of the metal concentrations were estimated quantities. With the exception of two total recoverable Cu values in Outfall C, all metal concentrations were below the permit limits and the federal water quality criteria. Ranges of TR for all outfalls were: Cd, ,0.1-0.4 {micro}g/L; Cr,1.07-3.93 {micro}g/L; Cu, 1.59-7.24 {micro}g/L; Pb, <0.1-3.20 {micro}g/L; Ni, 0.82-10.7 {micro}g/L, Zn, 4.75-67.3 {micro}g/L. DM:TRM ratios were developed for each outfall. The proportion of dissolved Cu in the effluents ranged from 67 to 82%; the proportion of dissolved Ni ranged from 84 to 91%; and the proportion of dissolved Zn ranged from 74 to 94%. The proportion of dissolved Pb in the effluents was considerably lower (37-51%). TRM and/or DM concentrations of Cu, Ni, Pb, or Zn differed significantly

  13. Development of site-specific soil cleanup criteria: New Brunswick Laboratory, New Jersey site

    SciTech Connect (OSTI)

    Veluri, V.R.; Moe, H.J.; Robinet, M.J.; Wynveen, R.A.

    1983-03-01

    The potential human exposure which results from the residual soil radioactivity at a decommissioned site is a prime concern during D and D projects. To estimate this exposure, a pathway analysis approach is often used to arrive at the residual soil radioactivity criteria. The development of such a criteria for the decommissioning of the New Brunswick Laboratory, New Jersey site is discussed. Contamination on this site was spotty and located in small soil pockets spread throughout the site area. Less than 1% of the relevant site area was contaminated. The major contaminants encountered at the site were /sup 239/Pu, /sup 241/Am, normal and natural uranium, and natural thorium. During the development of the pathway analysis to determine the site cleanup criteria, corrections for the inhomogeneity of the contamination were made. These correction factors and their effect upon the relevant pathway parameters are presented. Major pathways by which radioactive material may reach an individual are identified and patterns of use are specified (scenario). Each pathway is modeled to estimate the transfer parameters along the given pathway, such as soil to air to man, etc. The transfer parameters are then combined with dose rate conversion factors (ICRP 30 methodology) to obtain soil concentration to dose rate conversion factors (pCi/g/mrem/yr). For an appropriate choice of annual dose equivalent rate, one can then arrive at a value for the residual soil concentration. Pathway modeling, transfer parameters, and dose rate factors for the three major pathways; inhalation, ingestion and external exposure, which are important for the NBL site, are discussed.

  14. Assessment of health-care waste disposal methods using a VIKOR-based fuzzy multi-criteria decision making method

    SciTech Connect (OSTI)

    Liu, Hu-Chen; Wu, Jing; Li, Ping

    2013-12-15

    Highlights: • Propose a VIKOR-based fuzzy MCDM technique for evaluating HCW disposal methods. • Linguistic variables are used to assess the ratings and weights for the criteria. • The OWA operator is utilized to aggregate individual opinions of decision makers. • A case study is given to illustrate the procedure of the proposed framework. - Abstract: Nowadays selection of the appropriate treatment method in health-care waste (HCW) management has become a challenge task for the municipal authorities especially in developing countries. Assessment of HCW disposal alternatives can be regarded as a complicated multi-criteria decision making (MCDM) problem which requires consideration of multiple alternative solutions and conflicting tangible and intangible criteria. The objective of this paper is to present a new MCDM technique based on fuzzy set theory and VIKOR method for evaluating HCW disposal methods. Linguistic variables are used by decision makers to assess the ratings and weights for the established criteria. The ordered weighted averaging (OWA) operator is utilized to aggregate individual opinions of decision makers into a group assessment. The computational procedure of the proposed framework is illustrated through a case study in Shanghai, one of the largest cities of China. The HCW treatment alternatives considered in this study include “incineration”, “steam sterilization”, “microwave” and “landfill”. The results obtained using the proposed approach are analyzed in a comparative way.

  15. Wind turbine performance: Methods and criteria for reliability of measured power curves

    SciTech Connect (OSTI)

    Griffin, D.A.

    1996-12-31

    In order to evaluate the performance of prototype turbines, and to quantify incremental changes in performance through field testing, Advanced Wind Turbines (AWT) has been developing methods and requirements for power curve measurement. In this paper, field test data is used to illustrate several issues and trends which have resulted from this work. Averaging and binning processes, data hours per wind-speed bin, wind turbulence levels, and anemometry methods are all shown to have significant impacts on the resulting power curves. Criteria are given by which the AWT power curves show a high degree of repeatability, and these criteria are compared and contrasted with current published standards for power curve measurement. 6 refs., 5 figs., 5 tabs.

  16. Methods and compositions for chromosome-specific staining

    DOE Patents [OSTI]

    Gray, Joe W.; Pinkel, Daniel

    2003-07-22

    Methods and compositions for chromosome-specific staining are provided. Compositions comprise heterogenous mixtures of labeled nucleic acid fragments having substantially complementary base sequences to unique sequence regions of the chromosomal DNA for which their associated staining reagent is specific. Methods include methods for making the chromosome-specific staining compositions of the invention, and methods for applying the staining compositions to chromosomes.

  17. Fisk-based criteria to support validation of detection methods for drinking water and air.

    SciTech Connect (OSTI)

    MacDonell, M.; Bhattacharyya, M.; Finster, M.; Williams, M.; Picel, K.; Chang, Y.-S.; Peterson, J.; Adeshina, F.; Sonich-Mullin, C.; Environmental Science Division; EPA

    2009-02-18

    This report was prepared to support the validation of analytical methods for threat contaminants under the U.S. Environmental Protection Agency (EPA) National Homeland Security Research Center (NHSRC) program. It is designed to serve as a resource for certain applications of benchmark and fate information for homeland security threat contaminants. The report identifies risk-based criteria from existing health benchmarks for drinking water and air for potential use as validation targets. The focus is on benchmarks for chronic public exposures. The priority sources are standard EPA concentration limits for drinking water and air, along with oral and inhalation toxicity values. Many contaminants identified as homeland security threats to drinking water or air would convert to other chemicals within minutes to hours of being released. For this reason, a fate analysis has been performed to identify potential transformation products and removal half-lives in air and water so appropriate forms can be targeted for detection over time. The risk-based criteria presented in this report to frame method validation are expected to be lower than actual operational targets based on realistic exposures following a release. Note that many target criteria provided in this report are taken from available benchmarks without assessing the underlying toxicological details. That is, although the relevance of the chemical form and analogues are evaluated, the toxicological interpretations and extrapolations conducted by the authoring organizations are not. It is also important to emphasize that such targets in the current analysis are not health-based advisory levels to guide homeland security responses. This integrated evaluation of chronic public benchmarks and contaminant fate has identified more than 200 risk-based criteria as method validation targets across numerous contaminants and fate products in drinking water and air combined. The gap in directly applicable values is

  18. An Approach to Industrial Stormwater Benchmarks: Establishing and Using Site-Specific Threshold Criteria at Lawrence Livermore National Laboratory

    SciTech Connect (OSTI)

    Campbell, C G; Mathews, S

    2006-09-07

    Current regulatory schemes use generic or industrial sector specific benchmarks to evaluate the quality of industrial stormwater discharges. While benchmarks can be a useful tool for facility stormwater managers in evaluating the quality stormwater runoff, benchmarks typically do not take into account site-specific conditions, such as: soil chemistry, atmospheric deposition, seasonal changes in water source, and upstream land use. Failing to account for these factors may lead to unnecessary costs to trace a source of natural variation, or potentially missing a significant local water quality problem. Site-specific water quality thresholds, established upon the statistical evaluation of historic data take into account these factors, are a better tool for the direct evaluation of runoff quality, and a more cost-effective trigger to investigate anomalous results. Lawrence Livermore National Laboratory (LLNL), a federal facility, established stormwater monitoring programs to comply with the requirements of the industrial stormwater permit and Department of Energy orders, which require the evaluation of the impact of effluent discharges on the environment. LLNL recognized the need to create a tool to evaluate and manage stormwater quality that would allow analysts to identify trends in stormwater quality and recognize anomalous results so that trace-back and corrective actions could be initiated. LLNL created the site-specific water quality threshold tool to better understand the nature of the stormwater influent and effluent, to establish a technical basis for determining when facility operations might be impacting the quality of stormwater discharges, and to provide ''action levels'' to initiate follow-up to analytical results. The threshold criteria were based on a statistical analysis of the historic stormwater monitoring data and a review of relevant water quality objectives.

  19. A RAPID AND SPECIFIC TITRIMETRIC METHOD FOR THE PRECISE DETERMINATION...

    Office of Scientific and Technical Information (OSTI)

    A RAPID AND SPECIFIC TITRIMETRIC METHOD FOR THE PRECISE DETERMINATION OF URANIUM USING IRON(II) SULPHATE AS REDUCTANT Citation Details In-Document Search Title: A RAPID AND ...

  20. Method To Identify Specific Inhibiutors Of Imp Dehydrogenase

    DOE Patents [OSTI]

    Collart, Frank R.; Huberman, Eliezer

    2000-11-28

    This invention relates to methods to identify specific inhibitors of the purine nucleotide synthesis enzyme, IMP dehydrogenase (IMPDH). IMPDH is an essential enzyme found in all free-living organisms from humans to bacteria and is an important therapeutic target. The invention allows the identification of specific inhibitors of any IMPDH enzyme which can be expressed in a functional form in a recombinant host cell. A variety of eukaryotic or prokaryotic host systems commonly used for the expression of recombinant proteins are suitable for the practice of the invention. The methods are amenable to high throughput systems for the screening of inhibitors generated by combinatorial chemistry or other methods such as antisense molecule production. Utilization of exogenous guanosine as a control component of the methods allows for the identification of inhibitors specific for IMPDH rather than other causes of decreased cell proliferation.

  1. Uniform Methods Project: Determining Energy Efficiency Savings for Specific

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

    Measures | Department of Energy Project: Determining Energy Efficiency Savings for Specific Measures Uniform Methods Project: Determining Energy Efficiency Savings for Specific Measures The first set of protocols for determining energy savings from energy efficiency measures and programs were published by the National Renewable Energy Laboratory (NREL) in April 2013. Funded by the Office of Electricity Delivery and Energy Reliability and the Office of Energy Efficiency and Renewable Energy,

  2. Methods for generating phosphorylation site-specific immunological reagents

    DOE Patents [OSTI]

    Anderson, Carl W.; Appella, Ettore; Sakaguchi, Kazuyasu

    2001-01-01

    The present invention provides methods for generating phosphorylation site-specific immunological reagents. More specifically, a phosphopeptide mimetic is incorporated into a polypeptide in place of a phosphorylated amino acid. The polypeptide is used as antigen by standard methods to generate either monoclonal or polyclonal antibodies which cross-react with the naturally phosphorylated polypeptide. The phosphopeptide mimetic preferably contains a non-hydrolyzable linkage from the appropriate carbon atom of the amino acid residue to a phosphate group. A preferred linkage is a CF.sub.2 group. Such a linkage is used to generate the phosphoserine mimetic F.sub.2 Pab, which is incorporated into a polypeptide sequence derived from p53 to produce antibodies which recognize a specific phosphorylation state of p53. A CF.sub.2 group linkage is also used to produce the phosphothreonine mimetic F.sub.2 Pmb, and to produce the phosphotyrosine mimetic, F.sub.2 Pmp.

  3. Microchip method for the enrichment of specific DNA sequences

    DOE Patents [OSTI]

    Mirzabekov, Andrei Darievich; Lysov, Yuri Petrovich; Shick, Valentine Vladimirovich; Dubiley, Svetlana Alekseevna

    1998-01-01

    A method for enriching specific genetic material sequences is provided, whereby oligonucleotide molecules complementary to the desired genetic material is first used to isolate the genetic material from a first source of genomic material. Then the genetic material is used as a label to isolate similar genetic sequences from other sources.

  4. Microchip method for the enrichment of specific DNA sequences

    DOE Patents [OSTI]

    Mirzabekov, A.D.; Lysov, Y.P.; Shick, V.V.; Dubiley, S.A.

    1998-12-22

    A method for enriching specific genetic material sequences is provided, whereby oligonucleotide molecules complementary to the desired genetic material is first used to isolate the genetic material from a first source of genomic material. Then the genetic material is used as a label to isolate similar genetic sequences from other sources. 4 figs.

  5. Methods of biological dosimetry employing chromosome-specific staining

    DOE Patents [OSTI]

    Gray, Joe W.; Pinkel, Daniel

    2000-01-01

    Methods and compositions for staining based upon nucleic acid sequence that employ nucleic acid probes are provided. Said methods produce staining patterns that can be tailored for specific cytogenetic analyses. Said probes are appropriate for in situ hybridization and stain both interphase and metaphase chromosomal material with reliable signals. The nucleic acid probes are typically of a complexity greater than 50 kb, the complexity depending upon the cytogenetic application. Methods are provided to disable the hybridization capacity of shared, high copy repetitive sequences and/or remove such sequences to provide for useful contrast. Still further methods are provided to produce chromosome-specific staining reagents which are made specific to the targeted chromosomal material, which can be one or more whole chromosomes, one or more regions on one or more chromosomes, subsets of chromosomes and/or the entire genome. Probes and test kits are provided for use in tumor cytogenetics, in the detection of disease related loci, in analysis of structural abnormalities, such as translocations, and for biological dosimetry. Further, methods and prenatal test kits are provided to stain targeted chromosomal material of fetal cells, including fetal cells obtained from maternal blood. Still further, the invention provides for automated means to detect and analyse chromosomal abnormalities.

  6. Methods And Compositions For Chromosome-Specific Staining

    DOE Patents [OSTI]

    Gray, Joe W.; Pinkel, Daniel

    2003-08-19

    Methods and compositions for staining based upon nucleic acid sequence that employ nucleic acid probes are provided. Said methods produce staining patterns that can be tailored for specific cytogenetic analyses. Said probes are appropriate for in situ hybridization and stain both interphase and metaphase chromosomal material with reliable signals. The nucleic acid probes are typically of a complexity greater than 50 kb, the complexity depending upon the cytogenetic application. Methods are provided to disable the hybridization capacity of shared, high copy repetitive sequences and/or remove such sequences to provide for useful contrast. Still further methods are provided to produce chromosome-specific staining reagents which are made specific to the targeted chromosomal material, which can be one or more whole chromosomes, one or more regions on one or more chromosomes, subsets of chromosomes and/or the entire genome. Probes and test kits are provided for use in tumor cytogenetics, in the detection of disease related loci, in analysis of structural abnormalities, such as translocations, and for biological dosimetry. Further, methods and prenatal test kits are provided to stain targeted chromosomal material of fetal cells, including fetal cells obtained from maternal blood. Still further, the invention provides for automated means to detect and analyse chromosomal abnormalities.

  7. Method of preparing high specific activity platinum-195m

    DOE Patents [OSTI]

    Mirzadeh, Saed; Du, Miting; Beets, Arnold L.; Knapp, Jr., Furn F.

    2004-06-15

    A method of preparing high-specific-activity .sup.195m Pt includes the steps of: exposing .sup.193 Ir to a flux of neutrons sufficient to convert a portion of the .sup.193 Ir to .sup.195m Pt to form an irradiated material; dissolving the irradiated material to form an intermediate solution comprising Ir and Pt; and separating the Pt from the Ir by cation exchange chromatography to produce .sup.195m Pt.

  8. Method for preparing high specific activity 177Lu

    DOE Patents [OSTI]

    Mirzadeh, Saed; Du, Miting; Beets, Arnold L.; Knapp, Jr., Furn F.

    2004-04-06

    A method of separating lutetium from a solution containing Lu and Yb, particularly reactor-produced .sup.177 Lu and .sup.177 Yb, includes the steps of: providing a chromatographic separation apparatus containing LN resin; loading the apparatus with a solution containing Lu and Yb; and eluting the apparatus to chromatographically separate the Lu and the Yb in order to produce high-specific-activity .sup.177 Yb.

  9. Structural acceptance criteria Remote Handling Building Tritium Extraction Facility

    SciTech Connect (OSTI)

    Mertz, G.

    1999-12-16

    This structural acceptance criteria contains the requirements for the structural analysis and design of the Remote Handling Building (RHB) in the Tritium Extraction Facility (TEF). The purpose of this acceptance criteria is to identify the specific criteria and methods that will ensure a structurally robust building that will safely perform its intended function and comply with the applicable Department of Energy (DOE) structural requirements.

  10. Periodic local MP2 method employing orbital specific virtuals

    SciTech Connect (OSTI)

    Usvyat, Denis Schütz, Martin; Maschio, Lorenzo

    2015-09-14

    We introduce orbital specific virtuals (OSVs) to represent the truncated pair-specific virtual space in periodic local Møller-Plesset perturbation theory of second order (LMP2). The OSVs are constructed by diagonalization of the LMP2 amplitude matrices which correspond to diagonal Wannier-function (WF) pairs. Only a subset of these OSVs is adopted for the subsequent OSV-LMP2 calculation, namely, those with largest contribution to the diagonal pair correlation energy and with the accumulated value of these contributions reaching a certain accuracy. The virtual space for a general (non diagonal) pair is spanned by the union of the two OSV sets related to the individual WFs of the pair. In the periodic LMP2 method, the diagonal LMP2 amplitude matrices needed for the construction of the OSVs are calculated in the basis of projected atomic orbitals (PAOs), employing very large PAO domains. It turns out that the OSVs are excellent to describe short range correlation, yet less appropriate for long range van der Waals correlation. In order to compensate for this bias towards short range correlation, we augment the virtual space spanned by the OSVs by the most diffuse PAOs of the corresponding minimal PAO domain. The Fock and overlap matrices in OSV basis are constructed in the reciprocal space. The 4-index electron repulsion integrals are calculated by local density fitting and, for distant pairs, via multipole approximation. New procedures for determining the fit-domains and the distant-pair lists, leading to higher efficiency in the 4-index integral evaluation, have been implemented. Generally, and in contrast to our previous PAO based periodic LMP2 method, the OSV-LMP2 method does not require anymore great care in the specification of the individual domains (to get a balanced description when calculating energy differences) and is in that sense a black box procedure. Discontinuities in potential energy surfaces, which may occur for PAO-based calculations if one is not

  11. Chapter 1: Introduction. Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures

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

    1: Introduction The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures Created as part of subcontract with period of performance September 2011 - December 2014 Hossein Haeri The Cadmus Group, Inc., Portland, Oregon NREL Technical Monitor: Charles Kurnik Subcontract Report NREL/SR-7A40-63417 February 2015 NREL is a national laboratory of the U.S. Department of Energy Office of Energy Efficiency & Renewable Energy Operated by the Alliance for

  12. The Uniform Methods Project: Methods For Determining Energy Efficiency Savings For Specific Measures

    Broader source: Energy.gov [DOE]

    This document provides a set of model protocols for determining energy and demand savings that result from specific energy efficiency measures implemented through state and utility efficiency programs. The methods described here are approaches that are―or are among―the most commonly used in the energy efficiency industry for certain measures or programs.

  13. Alternative methods for dispoal of low-level radioactive wastes. Task 1. Description of methods and assessment of criteria. [Alternative methods are belowground vaults, aboveground vaults; earth mounded concrete bunkers, mined cavities, augered holes

    SciTech Connect (OSTI)

    Bennett, R.D.; Miller, W.O.; Warriner, J.B.; Malone, P.G.; McAneny, C.C.

    1984-04-01

    The study reported herein contains the results of Task 1 of a four-task study entitled Criteria for Evaluating Engineered Facilities. The overall objective of this study is to ensure that the criteria needed to evaluate five alternative low-level radioactive waste (LLW) disposal methods are available to the Nuclear Regulatory Commission (NRC) and the Agreement States. The alternative methods considered are belowground vaults, aboveground vaults, earth mounded concrete bunkers, mined cavities, and augered holes. Each of these alternatives is either being used by other countries for low-level radioactive waste (LLW) disposal or is being considered by other countries or US agencies. In this report the performance requirements are listed, each alternative is described, the experience gained with its use is discussed, and the performance capabilities of each method are addressed. Next, the existing 10 CFR Part 61 Subpart D criteria with respect to paragraphs 61.50 through 61.53, pertaining to site suitability, design, operations and closure, and monitoring are assessed for applicability to evaluation of each alternative. Preliminary conclusions and recommendations are offered on each method's suitability as an LLW disposal alternative, the applicability of the criteria, and the need for supplemental or modified criteria.

  14. Evaluation Criteria

    Broader source: Energy.gov [DOE]

    Applications must meet the basic eligibility criteria. Final decisions regarding eligibility and compliance will be made by the Office of Energy Efficiency and Renewable Energy (EERE).

  15. Nested methylation-specific polymerase chain reaction cancer detection method

    DOE Patents [OSTI]

    Belinsky, Steven A.; Palmisano, William A.

    2007-05-08

    A molecular marker-based method for monitoring and detecting cancer in humans. Aberrant methylation of gene promoters is a marker for cancer risk in humans. A two-stage, or "nested" polymerase chain reaction method is disclosed for detecting methylated DNA sequences at sufficiently high levels of sensitivity to permit cancer screening in biological fluid samples, such as sputum, obtained non-invasively. The method is for detecting the aberrant methylation of the p16 gene, O 6-methylguanine-DNA methyltransferase gene, Death-associated protein kinase gene, RAS-associated family 1 gene, or other gene promoters. The method offers a potentially powerful approach to population-based screening for the detection of lung and other cancers.

  16. Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures; January 2012 - March 2013

    SciTech Connect (OSTI)

    Jayaweera, T.; Haeri, H.

    2013-04-01

    Under the Uniform Methods Project, DOE is developing a framework and a set of protocols for determining the energy savings from specific energy efficiency measures and programs. The protocols provide a straightforward method for evaluating gross energy savings for common residential and commercial measures offered in ratepayer-funded initiatives in the United States. They represent a refinement of the body of knowledge supporting energy efficiency evaluation, measurement, and verification (EM&V) activities. This document deals with savings from the following measures: commercial and industrial lighting, commercial and industrial lighting controls, small commercial and residential unitary and split system HVAC cooling equipment, residential furnaces and boilers, residential lighting, refrigerator recycling, whole-building retrofit using billing analysis, metering, peak demand and time-differentiated energy savings, sample design, survey design and implementation, and assessing persistence and other evaluation issues.

  17. specifications

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

    specifications - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Energy Defense Waste Management Programs Advanced Nuclear

  18. Comparison of methods applicable to evaluation of nuclear power plant technical specifications

    SciTech Connect (OSTI)

    Cho, N.Z.; Bozoki, G.E.; Youngblood, R.W.

    1986-01-01

    The sample problem devised in this study is to calculate core damage frequencies for different allowed outage times (AOTs) from an accident sequence using the three methods: (1) static fault tree approach, (2) time-dependent unavailability analysis, and (3) Markov analysis. The results obtained in this study give useful insights and lend confidence to the conclusion that the static fault tree approach can be used by NRC for the AOT problem when the quantified higher level measures, e.g., core damage frequency and health risks, turn out to be unequivocally below the criteria (e.g., the safety goals). However, when the higher level measures corresponding to the proposed AOTs are in the range of the criteria, the Markov analysis or the time-dependent unavailability analysis would be attractive to owners of the plants who bear the burden of proof in AOT relaxation. 7 refs., 2 figs.

  19. Chapter 7, Refrigerator Recycling Evaluation Protocol: The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures

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

    7: Refrigerator Recycling Evaluation Protocol Doug Bruchs and Josh Keeling, The Cadmus Group, Inc. Subcontract Report NREL/SR-7A30-53827 April 2013 The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures 7 - 1 Chapter 7 - Table of Contents 1 Measure Description .............................................................................................................. 2 2 Application Conditions of Protocol

  20. Chapter 21: Residential Lighting Evaluation Protocol. Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures

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

    1: Residential Lighting Evaluation Protocol The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures Created as part of subcontract with period of performance September 2011 - December 2014 This supersedes the version originally published in April 2013. Scott Dimetrosky, Katie Parkinson, and Noah Lieb Apex Analytics, LLC Boulder, Colorado NREL Technical Monitor: Charles Kurnik Subcontract Report NREL/SR-7A40-63205 February 2015 NREL is a national

  1. The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures: January 2012 - March 2013

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

    Contract No. DE-AC36-08GO28308 The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures January 2012 - March 2013 Tina Jayaweera Hossein Haeri The Cadmus Group Portland, Oregon NREL Technical Monitor: Charles Kurnik Subcontract Report NREL/SR-7A30-53827 April 2013 NREL is a national laboratory of the U.S. Department of Energy, Office of Energy Efficiency & Renewable Energy, operated by the Alliance for Sustainable Energy, LLC. National Renewable

  2. Method to Produce High Specific Impulse and Moderate Thrust from a

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

    Fusion-powered Rocket Engine: (ARE-Aneutronic Rocket Engine) --- Inventor(s) Samuel A. Cohen, Michael Paluszek, Yosef Razin, and Gary Pajer | Princeton Plasma Physics Lab Method to Produce High Specific Impulse and Moderate Thrust from a Fusion-powered Rocket Engine: (ARE-Aneutronic Rocket Engine) --- Inventor(s) Samuel A. Cohen, Michael Paluszek, Yosef Razin, and Gary Pajer This Invention describes a fusion-powered rocket engine that will produce high specific impulse, Isp, moderate thrust,

  3. Method for promoting specific alignment of short oligonucleotides on nucleic acids

    DOE Patents [OSTI]

    Studier, F. William; Kieleczawa, Jan; Dunn, John J.

    1996-01-01

    Disclosed is a method for promoting specific alignment of short oligonucleotides on a nucleic acid polymer. The nucleic acid polymer is incubated in a solution containing a single-stranded DNA-binding protein and a plurality of oligonucleotides which are perfectly complementary to distinct but adjacent regions of a predetermined contiguous nucleotide sequence in the nucleic acid polymer. The plurality of oligonucleotides anneal to the nucleic acid polymer to form a contiguous region of double stranded nucleic acid. Specific application of the methods disclosed include priming DNA synthesis and template-directed ligation.

  4. Repeat sequence chromosome specific nucleic acid probes and methods of preparing and using

    DOE Patents [OSTI]

    Weier, Heinz-Ulrich G.; Gray, Joe W.

    1995-01-01

    A primer directed DNA amplification method to isolate efficiently chromosome-specific repeated DNA wherein degenerate oligonucleotide primers are used is disclosed. The probes produced are a heterogeneous mixture that can be used with blocking DNA as a chromosome-specific staining reagent, and/or the elements of the mixture can be screened for high specificity, size and/or high degree of repetition among other parameters. The degenerate primers are sets of primers that vary in sequence but are substantially complementary to highly repeated nucleic acid sequences, preferably clustered within the template DNA, for example, pericentromeric alpha satellite repeat sequences. The template DNA is preferably chromosome-specific. Exemplary primers ard probes are disclosed. The probes of this invention can be used to determine the number of chromosomes of a specific type in metaphase spreads, in germ line and/or somatic cell interphase nuclei, micronuclei and/or in tissue sections. Also provided is a method to select arbitrarily repeat sequence probes that can be screened for chromosome-specificity.

  5. Repeat sequence chromosome specific nucleic acid probes and methods of preparing and using

    DOE Patents [OSTI]

    Weier, H.U.G.; Gray, J.W.

    1995-06-27

    A primer directed DNA amplification method to isolate efficiently chromosome-specific repeated DNA wherein degenerate oligonucleotide primers are used is disclosed. The probes produced are a heterogeneous mixture that can be used with blocking DNA as a chromosome-specific staining reagent, and/or the elements of the mixture can be screened for high specificity, size and/or high degree of repetition among other parameters. The degenerate primers are sets of primers that vary in sequence but are substantially complementary to highly repeated nucleic acid sequences, preferably clustered within the template DNA, for example, pericentromeric alpha satellite repeat sequences. The template DNA is preferably chromosome-specific. Exemplary primers and probes are disclosed. The probes of this invention can be used to determine the number of chromosomes of a specific type in metaphase spreads, in germ line and/or somatic cell interphase nuclei, micronuclei and/or in tissue sections. Also provided is a method to select arbitrarily repeat sequence probes that can be screened for chromosome-specificity. 18 figs.

  6. Proposal Writing Guidelines and Scoring Criteria

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

    when the reasons for choosing a specific beamline are clearly stated, e.g., unique features, required resolution, higher flux, etc. Criteria for Evaluating the Scientific...

  7. Nucleotide sequences specific to Francisella tularensis and methods for the detection of Francisella tularensis

    DOE Patents [OSTI]

    McCready, Paula M.; Radnedge, Lyndsay; Andersen, Gary L.; Ott, Linda L.; Slezak, Thomas R.; Kuczmarski, Thomas A.; Vitalis, Elizabeth A

    2009-02-24

    Described herein is the identification of nucleotide sequences specific to Francisella tularensis that serves as a marker or signature for identification of this bacterium. In addition, forward and reverse primers and hybridization probes derived from these nucleotide sequences that are used in nucleotide detection methods to detect the presence of the bacterium are disclosed.

  8. Nucleotide sequences specific to Brucella and methods for the detection of Brucella

    DOE Patents [OSTI]

    McCready, Paula M.; Radnedge, Lyndsay; Andersen, Gary L.; Ott, Linda L.; Slezak, Thomas R.; Kuczmarski, Thomas A.

    2009-02-24

    Nucleotide sequences specific to Brucella that serves as a marker or signature for identification of this bacterium were identified. In addition, forward and reverse primers and hybridization probes derived from these nucleotide sequences that are used in nucleotide detection methods to detect the presence of the bacterium are disclosed.

  9. Nucleotide sequences specific to Yersinia pestis and methods for the detection of Yersinia pestis

    DOE Patents [OSTI]

    McCready, Paula M.; Radnedge, Lyndsay; Andersen, Gary L.; Ott, Linda L.; Slezak, Thomas R.; Kuczmarski, Thomas A.; Motin, Vladinir L.

    2009-02-24

    Nucleotide sequences specific to Yersinia pestis that serve as markers or signatures for identification of this bacterium were identified. In addition, forward and reverse primers and hybridization probes derived from these nucleotide sequences that are used in nucleotide detection methods to detect the presence of the bacterium are disclosed.

  10. Nucleotide sequences specific to Francisella tularensis and methods for the detection of Francisella tularensis

    DOE Patents [OSTI]

    McCready, Paula M.; Radnedge, Lyndsay; Andersen, Gary L.; Ott, Linda L.; Slezak, Thomas R.; Kuczmarski, Thomas A.; Vitalis, Elizabeth A

    2007-02-06

    Described herein is the identification of nucleotide sequences specific to Francisella tularensis that serves as a marker or signature for identification of this bacterium. In addition, forward and reverse primers and hybridization probes derived from these nucleotide sequences that are used in nucleotide detection methods to detect the presence of the bacterium are disclosed.

  11. Y chromosome specific nucleic acid probe and method for determining the Y chromosome in situ

    DOE Patents [OSTI]

    Gray, Joe W.; Weier, Heinz-Ulrich

    2001-01-01

    A method for producing a Y chromosome specific probe selected from highly repeating sequences on that chromosome is described. There is little or no nonspecific binding to autosomal and X chromosomes, and a very large signal is provided. Inventive primers allowing the use of PCR for both sample amplification and probe production are described, as is their use in producing large DNA chromosome painting sequences.

  12. Y chromosome specific nucleic acid probe and method for determining the Y chromosome in situ

    DOE Patents [OSTI]

    Gray, J.W.; Weier, H.U.

    1998-11-24

    A method for producing a Y chromosome specific probe selected from highly repeating sequences on that chromosome is described. There is little or no nonspecific binding to autosomal and X chromosomes, and a very large signal is provided. Inventive primers allowing the use of PCR for both sample amplification and probe production are described, as is their use in producing large DNA chromosome painting sequences. 9 figs.

  13. Y chromosome specific nucleic acid probe and method for determining the Y chromosome in situ

    DOE Patents [OSTI]

    Gray, Joe W.; Weier, Heinz-Ulrich

    1998-01-01

    A method for producing a Y chromosome specific probe selected from highly repeating sequences on that chromosome is described. There is little or no nonspecific binding to autosomal and X chromosomes, and a very large signal is provided. Inventive primers allowing the use of PCR for both sample amplification and probe production are described, as is their use in producing large DNA chromosome painting sequences.

  14. Y chromosome specific nucleic acid probe and method for identifying the Y chromosome in SITU

    DOE Patents [OSTI]

    Gray, J.W.; Weier, H.U.

    1999-03-30

    A method for producing a Y chromosome specific probe selected from highly repeating sequences on that chromosome is described. There is little or no nonspecific binding to autosomal and X chromosomes, and a very large signal is provided. Inventive primers allowing the use of PCR for both sample amplification and probe production are described, as is their use in producing large DNA chromosome painting sequences. 9 figs.

  15. Y chromosome specific nucleic acid probe and method for identifying the Y chromosome in SITU

    DOE Patents [OSTI]

    Gray, Joe W.; Weier, Heinz-Ulrich

    1999-01-01

    A method for producing a Y chromosome specific probe selected from highly repeating sequences on that chromosome is described. There is little or no nonspecific binding to autosomal and X chromosomes, and a very large signal is provided. Inventive primers allowing the use of PCR for both sample amplification and probe production are described, as is their use in producing large DNA chromosome painting sequences.

  16. Method for indexing and retrieving manufacturing-specific digital imagery based on image content

    DOE Patents [OSTI]

    Ferrell, Regina K.; Karnowski, Thomas P.; Tobin, Jr., Kenneth W.

    2004-06-15

    A method for indexing and retrieving manufacturing-specific digital images based on image content comprises three steps. First, at least one feature vector can be extracted from a manufacturing-specific digital image stored in an image database. In particular, each extracted feature vector corresponds to a particular characteristic of the manufacturing-specific digital image, for instance, a digital image modality and overall characteristic, a substrate/background characteristic, and an anomaly/defect characteristic. Notably, the extracting step includes generating a defect mask using a detection process. Second, using an unsupervised clustering method, each extracted feature vector can be indexed in a hierarchical search tree. Third, a manufacturing-specific digital image associated with a feature vector stored in the hierarchicial search tree can be retrieved, wherein the manufacturing-specific digital image has image content comparably related to the image content of the query image. More particularly, can include two data reductions, the first performed based upon a query vector extracted from a query image. Subsequently, a user can select relevant images resulting from the first data reduction. From the selection, a prototype vector can be calculated, from which a second-level data reduction can be performed. The second-level data reduction can result in a subset of feature vectors comparable to the prototype vector, and further comparable to the query vector. An additional fourth step can include managing the hierarchical search tree by substituting a vector average for several redundant feature vectors encapsulated by nodes in the hierarchical search tree.

  17. Method for the determination of technical specifications limiting temperature in EBR-II operation

    SciTech Connect (OSTI)

    Chang, L.K.; Hill, D.J.; Ku, J.Y.

    1994-03-01

    The methodology and analysis procedure to qualify the Mark-V and Mark-VA fuels for the Experimental Breeder Reactor II are summarized in this paper. Fuel performance data and design safety criteria are essential for thermal-hydraulic analysis and safety evaluations. Normal and off-normal operation duty cycles and transient classifications are required for the safety assessment of the fuels. The temperature limits of subassemblies were first determined by a steady-state thermal-structural and fuel damage analysis, in which a trial-and-error approach was used to predict the maximum allowable fuel pin temperature that satisfies the design criteria for steady-state normal operation. The steady-state temperature limits were used as the basis of the off-normal transient analysis to assess the safety performance of the fuel for anticipated, unlikely and extremely unlikely events. If the design criteria for the off-normal events are not satisfied, then the subassembly temperature limit is reduced and an iterative procedure is employed until all design criteria are met.

  18. ARM - Guidelines : Review Criteria

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

    Review Criteria Guidelines Overview Annual Facility Call Proposal Deadline Guidance Small Field Campaigns Review Criteria Expectations for Principal Investigators Forms Propose a Campaign Instrument Support Request (ISR) Form (Word, 89KB) Unmanned Aerial System (UAS) Mission Request Form (Word, 72KB) Documentation Submitting Field Campaign Data and Metadata Field Campaign Guidelines (PDF, 574KB) Unmanned Aerial System Operation Safety at ARM Sites (PDF, 639KB) Guidelines : Review Criteria

  19. Acceptance Criteria - Hanford Site

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

    G and I clarified requirements throughout the appendices. Appendix I, Table I-1 in the Waste Acceptance Criteria for the "Payload Container Description" removed "208-L (55 gal)...

  20. ROC analysis in patient specific quality assurance

    SciTech Connect (OSTI)

    Carlone, Marco; MacPherson, Miller; Cruje, Charmainne; Rangel, Alejandra; McCabe, Ryan; Nielsen, Michelle

    2013-04-15

    Purpose: This work investigates the use of receiver operating characteristic (ROC) methods in patient specific IMRT quality assurance (QA) in order to determine unbiased methods to set threshold criteria for {gamma}-distance to agreement measurements. Methods: A group of 17 prostate plans was delivered as planned while a second group of 17 prostate plans was modified with the introduction of random multileaf collimator (MLC) position errors that are normally distributed with {sigma}{approx}{+-}0.5, {+-}1.0, {+-}2.0, and {+-}3.0 mm (a total of 68 modified plans were created). All plans were evaluated using five different {gamma}-criteria. ROC methodology was applied by quantifying the fraction of modified plans reported as 'fail' and unmodified plans reported as 'pass.'Results: {gamma}-based criteria were able to attain nearly 100% sensitivity/specificity in the detection of large random errors ({sigma} > 3 mm). Sensitivity and specificity decrease rapidly for all {gamma}-criteria as the size of error to be detected decreases below 2 mm. Predictive power is null with all criteria used in the detection of small MLC errors ({sigma} < 0.5 mm). Optimal threshold values were established by determining which criteria maximized sensitivity and specificity. For 3%/3 mm {gamma}-criteria, optimal threshold values range from 92% to 99%, whereas for 2%/2 mm, the range was from 77% to 94%. Conclusions: The optimal threshold values that were determined represent a maximized test sensitivity and specificity and are not subject to any user bias. When applied to the datasets that we studied, our results suggest the use of patient specific QA as a safety tool that can effectively prevent large errors (e.g., {sigma} > 3 mm) as opposed to a tool to improve the quality of IMRT delivery.

  1. Accident analysis and DOE criteria

    SciTech Connect (OSTI)

    Graf, J.M.; Elder, J.C.

    1982-01-01

    In analyzing the radiological consequences of major accidents at DOE facilities one finds that many facilities fall so far below the limits of DOE Order 6430 that compliance is easily demonstrated by simple analysis. For those cases where the amount of radioactive material and the dispersive energy available are enough for accident consequences to approach the limits, the models and assumptions used become critical. In some cases the models themselves are the difference between meeting the criteria or not meeting them. Further, in one case, we found that not only did the selection of models determine compliance but the selection of applicable criteria from different chapters of Order 6430 also made the difference. DOE has recognized the problem of different criteria in different chapters applying to one facility, and has proceeded to make changes for the sake of consistency. We have proposed to outline the specific steps needed in an accident analysis and suggest appropriate models, parameters, and assumptions. As a result we feed DOE siting and design criteria will be more fairly and consistently applied.

  2. Plutonium storage criteria

    SciTech Connect (OSTI)

    Chung, D.; Ascanio, X.

    1996-05-01

    The Department of Energy has issued a technical standard for long-term (>50 years) storage and will soon issue a criteria document for interim (<20 years) storage of plutonium materials. The long-term technical standard, {open_quotes}Criteria for Safe Storage of Plutonium Metals and Oxides,{close_quotes} addresses the requirements for storing metals and oxides with greater than 50 wt % plutonium. It calls for a standardized package that meets both off-site transportation requirements, as well as remote handling requirements from future storage facilities. The interim criteria document, {open_quotes}Criteria for Interim Safe Storage of Plutonium-Bearing Solid Materials{close_quotes}, addresses requirements for storing materials with less than 50 wt% plutonium. The interim criteria document assumes the materials will be stored on existing sites, and existing facilities and equipment will be used for repackaging to improve the margin of safety.

  3. METHOD AND APPARATUS FOR TESTING THE PRESENCE OF SPECIFIC ATOMIC ELEMENTS IN A SUBSTANCE

    DOE Patents [OSTI]

    Putman, J.L.

    1960-01-26

    Detection of specific atomic elements in a substance and particularly the applicability to well logging are discussed. The principal novelty resides in the determination of several of the auxiliary energy peaks in addition to the main energy peak of the gamma-ray energy spectrum of a substance and comparison of such peaks to the spectrum of the specific atomic element being tested for. thus resulting in identification of same. The invention facilitates the identification of specific elements even when in the presence of other elements having similar gamma energy spectra as to the main energy peaks.

  4. Chapter 10, Peak Demand and Time-Differentiated Energy Savings Cross-Cutting Protocols: The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures

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

    0: Peak Demand and Time-Differentiated Energy Savings Cross-Cutting Protocols Frank Stern, Navigant Consulting Subcontract Report NREL/SR-7A30-53827 April 2013 The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures 10 - 1 Chapter 10 - Table of Contents 1 Introduction .............................................................................................................................2 2 Purpose of Peak Demand and Time-differentiated Energy

  5. Chapter 11, Sample Design Cross-Cutting Protocols: The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures

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

    1: Sample Design Cross-Cutting Protocols M. Sami Khawaja, Josh Rushton, and Josh Keeling, The Cadmus Group, Inc. Subcontract Report NREL/SR-7A30-53827 April 2013 The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures 11 - 1 Chapter 11 - Table of Contents 1 Introduction ............................................................................................................................ 3 1.1 Chapter Organization

  6. Chapter 13, Assessing Persistence and Other Evaluation Issues Cross-Cutting Protocols: The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures

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

    3: Assessing Persistence and Other Evaluation Issues Cross- Cutting Protocols Daniel M. Violette, Navigant Consulting Subcontract Report NREL/SR-7A30-53827 April 2013 The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures 13 - 1 Chapter 13 - Table of Contents 1 Introduction .............................................................................................................................2 2 Persistence of Energy Savings

  7. Chapter 2, Commercial and Industrial Lighting Evaluation Protocol: The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures

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

    2: Commercial and Industrial Lighting Evaluation Protocol The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures Dakers Gowans, Left Fork Energy Subcontract Report NREL/SR-7A30-53827 April 2013 Chapter 2 - Table of Contents 1 Measure Description .............................................................................................................. 2 2 Application Conditions of the Protocol

  8. Chapter 3, Commercial and Industrial Lighting Controls Evaluation Protocol: The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures

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

    3: Commercial and Industrial Lighting Controls Evaluation Protocol Stephen Carlson, DNV KEMA Subcontract Report NREL/SR-7A30-53827 April 2013 The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures 3 - 1 Chapter 3 - Table of Contents 1 Measure Description .............................................................................................................. 2 2 Application Conditions of Protocol

  9. Chapter 5, Residential Furnaces and Boilers Evaluation Protocol: The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures

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

    5: Residential Furnaces and Boilers Evaluation Protocol David Jacobson, Jacobson Energy Research Subcontract Report NREL/SR-7A30-53827 April 2013 The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures 5 - 1 Chapter 5 - Table of Contents 1 Measure Description .............................................................................................................. 2 2 Application Conditions of Protocol

  10. Chapter 8, Whole-Building Retrofit with Billing Analysis Evaluation Protocol: The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures

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

    8: Whole-Building Retrofit with Consumption Data Analysis Evaluation Protocol Ken Agnew and Mimi Goldberg, DNV KEMA Subcontract Report NREL/SR-7A30-53827 April 2013 The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures 8 - 1 Chapter 8 - Table of Contents 1 Measure Description ...............................................................................................................2 2 Application Conditions of Protocol

  11. Fire protection design criteria

    SciTech Connect (OSTI)

    1997-03-01

    This Standard provides supplemental fire protection guidance applicable to the design and construction of DOE facilities and site features (such as water distribution systems) that are also provided for fire protection. It is intended to be used in conjunction with the applicable building code, national Fire Protection Association Codes and Standards, and any other applicable DOE construction criteria. This Standard, along with other delineated criteria, constitutes the basic criteria for satisfying DOE fire and life safety objectives for the design and construction or renovation of DOE facilities.

  12. Worker-specific exposure monitor and method for surveillance of workers

    DOE Patents [OSTI]

    Lovejoy, Michael L.; Peeters, John P.; Johnson, A. Wayne

    2000-01-01

    A person-specific monitor that provides sensor information regarding hazards to which the person is exposed and means to geolocate the person at the time of the exposure. The monitor also includes means to communicate with a remote base station. Information from the monitor can be downloaded at the base station for long term storage and analysis. The base station can also include means to recharge the monitor.

  13. Chapter 14: Chiller Evaluation Protocol. The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures: September 2011 … May 2015

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

    4: Chiller Evaluation Protocol The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures Created as part of subcontract with period of performance September 2011 - December 2014 Alex Tiessen, Posterity Group Ottawa, Ontario NREL Technical Monitor: Charles Kurnik Subcontract Report NREL/SR-7A40-62431 September 2014 NREL is a national laboratory of the U.S. Department of Energy Office of Energy Efficiency & Renewable Energy Operated by the Alliance

  14. Chapter 15: Commercial New Construction Protocol. The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures: September 2011 … May 2015

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

    5: Commercial New Construction Protocol The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures Created as part of subcontract with period of performance September 2011 - December 2014 Steven Keates, ADM Associates, Inc. Sacramento, California NREL Technical Monitor: Charles Kurnik Subcontract Report NREL/SR-7A40-62432 September 2014 NREL is a national laboratory of the U.S. Department of Energy Office of Energy Efficiency & Renewable Energy

  15. Chapter 16: Retrocommissioning Evaluation Protocol. The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures: September 2011 … May 2015

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

    6: Retrocommissioning Evaluation Protocol The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures Created as part of subcontract with period of performance September 2011 - December 2014 Alex Tiessen, Posterity Group Ottawa, Ontario NREL Technical Monitor: Charles Kurnik Subcontract Report NREL/SR-7A40-62430 September 2014 NREL is a national laboratory of the U.S. Department of Energy Office of Energy Efficiency & Renewable Energy Operated by the

  16. Chapter 18: Variable Frequency Drive Evaluation Protocol. The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures: September 2011 … December 2014

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

    8: Variable Frequency Drive Evaluation Protocol The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures Created as part of subcontract with period of performance September 2011 - December 2014 Jeff Romberger SBW Consulting, Inc. Bellevue, Washington NREL Technical Monitor: Charles Kurnik Subcontract Report NREL/SR-7A40-63166 November 2014 NREL is a national laboratory of the U.S. Department of Energy Office of Energy Efficiency & Renewable Energy

  17. Chapter 19: HVAC Controls (DDC/EMS/BAS) Evaluation Protocol. The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures: September 2011 … December 2014

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

    9: HVAC Controls (DDC/EMS/BAS) Evaluation Protocol The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures Created as part of subcontract with period of performance September 2011 - December 2014 Jeff Romberger SBW Consulting, Inc. Bellevue, Washington NREL Technical Monitor: Charles Kurnik Subcontract Report NREL/SR-7A40-63167 November 2014 NREL is a national laboratory of the U.S. Department of Energy Office of Energy Efficiency & Renewable

  18. Chapter 20: Data Center IT Efficiency Measures. The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures; Period of Performance: September 2011 … December 2014

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

    0: Data Center IT Efficiency Measures The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures Created as part of subcontract with period of performance September 2011 - December 2014 Robert Huang The Cadmus Group, Inc. Waltham, Massachusetts Eric Masanet Northwestern University Evanston, Illinois NREL Technical Monitor: Charles Kurnik Subcontract Report NREL/SR-7A40-63181 January 2015 NREL is a national laboratory of the U.S. Department of Energy

  19. Chapter 22: Compressed Air Evaluation Protocol. The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures: September 2011 … December 2014

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

    2: Compressed Air Evaluation Protocol The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures Created as part of subcontract with period of performance September 2011 - December 2014 Nathanael Benton Nexant, Inc. San Francisco, California NREL Technical Monitor: Charles Kurnik Subcontract Report NREL/SR-7A40-63210 November 2014 NREL is a national laboratory of the U.S. Department of Energy Office of Energy Efficiency & Renewable Energy Operated by

  20. Chapter 23: Estimating Net Savings: Common Practices. The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures: September 2011 … December 2014

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

    3: Estimating Net Savings: Common Practices The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures Created as part of subcontract with period of performance September 2011 - December 2014 Daniel M. Violette, Ph.D. Navigant, Boulder, Colorado Pamela Rathbun, Tetra Tech, Madison, Wisconsin NREL Technical Monitor: Charles Kurnik Subcontract Report NREL/SR-7A40-62678 September 2014 NREL is a national laboratory of the U.S. Department of Energy Office of

  1. Method for high specific bioproductivity of .alpha.,.omega.-alkanedicarboxylic acids

    DOE Patents [OSTI]

    Mobley, David Paul; Shank, Gary Keith

    2000-01-01

    This invention provides a low-cost method of producing .alpha.,.omega.-alkanedicarboxylic acids. Particular bioconversion conditions result in highly efficient conversion of fatty acid, fatty acid ester, or alkane substrates to diacids. Candida tropicalis AR40 or similar yeast strains are grown in a medium containing a carbon source and a nitrogen source at a temperature of 31.degree. C. to 38.degree. C., while additional carbon source is continuously added, until maximum cell growth is attained. Within 0-3 hours of this point, substrate is added to the culture to initiate conversion. An .alpha.,.omega.-alkanedicarboxylic acid made according to this method is also provided.

  2. Methods of and apparatus for radiation measurement, and specifically for in vivo radiation measurement

    DOE Patents [OSTI]

    Huffman, D.D.; Hughes, R.C.; Kelsey, C.A.; Lane, R.; Ricco, A.J.; Snelling, J.B.; Zipperian, T.E.

    1986-08-29

    Methods of and apparatus for in vivo radiation measurements rely on a MOSFET dosimeter of high radiation sensitivity which operates in both the passive mode to provide an integrated dose detector and active mode to provide an irradiation rate detector. A compensating circuit with a matched unirradiated MOSFET is provided to operate at a current designed to eliminate temperature dependence of the device. Preferably, the MOSFET is rigidly mounted in the end of a miniature catheter and the catheter is implanted in the patient proximate the radiation source.

  3. Method for the detection of specific nucleic acid sequences by polymerase nucleotide incorporation

    DOE Patents [OSTI]

    Castro, Alonso

    2004-06-01

    A method for rapid and efficient detection of a target DNA or RNA sequence is provided. A primer having a 3'-hydroxyl group at one end and having a sequence of nucleotides sufficiently homologous with an identifying sequence of nucleotides in the target DNA is selected. The primer is hybridized to the identifying sequence of nucleotides on the DNA or RNA sequence and a reporter molecule is synthesized on the target sequence by progressively binding complementary nucleotides to the primer, where the complementary nucleotides include nucleotides labeled with a fluorophore. Fluorescence emitted by fluorophores on single reporter molecules is detected to identify the target DNA or RNA sequence.

  4. Method for performing site-specific affinity fractionation for use in DNA sequencing

    DOE Patents [OSTI]

    Mirzabekov, Andrei Darievich; Lysov, Yuri Petrovich; Dubley, Svetlana A.

    1999-01-01

    A method for fractionating and sequencing DNA via affinity interaction is provided comprising contacting cleaved DNA to a first array of oligonucleotide molecules to facilitate hybridization between said cleaved DNA and the molecules; extracting the hybridized DNA from the molecules; contacting said extracted hybridized DNA with a second array of oligonucleotide molecules, wherein the oligonucleotide molecules in the second array have specified base sequences that are complementary to said extracted hybridized DNA; and attaching labeled DNA to the second array of oligonucleotide molecules, wherein the labeled re-hybridized DNA have sequences that are complementary to the oligomers. The invention further provides a method for performing multi-step conversions of the chemical structure of compounds comprising supplying an array of polyacrylamide vessels separated by hydrophobic surfaces; immobilizing a plurality of reactants, such as enzymes, in the vessels so that each vessel contains one reactant; contacting the compounds to each of the vessels in a predetermined sequence and for a sufficient time to convert the compounds to a desired state; and isolating the converted compounds from said array.

  5. Method for performing site-specific affinity fractionation for use in DNA sequencing

    DOE Patents [OSTI]

    Mirzabekov, A.D.; Lysov, Y.P.; Dubley, S.A.

    1999-05-18

    A method for fractionating and sequencing DNA via affinity interaction is provided comprising contacting cleaved DNA to a first array of oligonucleotide molecules to facilitate hybridization between the cleaved DNA and the molecules; extracting the hybridized DNA from the molecules; contacting the extracted hybridized DNA with a second array of oligonucleotide molecules, wherein the oligonucleotide molecules in the second array have specified base sequences that are complementary to the extracted hybridized DNA; and attaching labeled DNA to the second array of oligonucleotide molecules, wherein the labeled re-hybridized DNA have sequences that are complementary to the oligomers. The invention further provides a method for performing multi-step conversions of the chemical structure of compounds comprising supplying an array of polyacrylamide vessels separated by hydrophobic surfaces; immobilizing a plurality of reactants, such as enzymes, in the vessels so that each vessel contains one reactant; contacting the compounds to each of the vessels in a predetermined sequence and for a sufficient time to convert the compounds to a desired state; and isolating the converted compounds from the array. 14 figs.

  6. Waste management project's alternatives: A risk-based multi-criteria assessment (RBMCA) approach

    SciTech Connect (OSTI)

    Karmperis, Athanasios C.; Sotirchos, Anastasios; Aravossis, Konstantinos; Tatsiopoulos, Ilias P.

    2012-01-15

    Highlights: Black-Right-Pointing-Pointer We examine the evaluation of a waste management project's alternatives. Black-Right-Pointing-Pointer We present a novel risk-based multi-criteria assessment (RBMCA) approach. Black-Right-Pointing-Pointer In the RBMCA the evaluation criteria are based on the quantitative risk analysis of the project's alternatives. Black-Right-Pointing-Pointer Correlation between the criteria weight values and the decision makers' risk preferences is examined. Black-Right-Pointing-Pointer Preference to the multi-criteria against the one-criterion evaluation process is discussed. - Abstract: This paper examines the evaluation of a waste management project's alternatives through a quantitative risk analysis. Cost benefit analysis is a widely used method, in which the investments are mainly assessed through the calculation of their evaluation indicators, namely benefit/cost (B/C) ratios, as well as the quantification of their financial, technical, environmental and social risks. Herein, a novel approach in the form of risk-based multi-criteria assessment (RBMCA) is introduced, which can be used by decision makers, in order to select the optimum alternative of a waste management project. Specifically, decision makers use multiple criteria, which are based on the cumulative probability distribution functions of the alternatives' B/C ratios. The RBMCA system is used for the evaluation of a waste incineration project's alternatives, where the correlation between the criteria weight values and the decision makers' risk preferences is analyzed and useful conclusions are discussed.

  7. Waste Specification Records - Hanford Site

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

    Specification Records About Us Hanford Site Solid Waste Acceptance Program What's New Acceptance Criteria Acceptance Process Becoming a new Hanford Customer Annual Waste Forecast...

  8. Performance Criteria and Evaluation System

    Energy Science and Technology Software Center (OSTI)

    1992-06-18

    The Performance Criteria and Evaluation System (PCES) was developed in order to make a data base of criteria accessible to radiation safety staff. The criteria included in the package are applicable to occupational radiation safety at DOE reactor and nonreactor nuclear facilities, but any data base of criteria may be created using the Criterion Data Base Utiliity (CDU). PCES assists personnel in carrying out oversight, line, and support activities.

  9. SU-E-I-40: New Method for Measurement of Task-Specific, High-Resolution Detector System Performance

    SciTech Connect (OSTI)

    Loughran, B; Singh, V; Jain, A; Bednarek, D; Rudin, S

    2014-06-01

    Purpose: Although generalized linear system analytic metrics such as GMTF and GDQE can evaluate performance of the whole imaging system including detector, scatter and focal-spot, a simplified task-specific measured metric may help to better compare detector systems. Methods: Low quantum-noise images of a neuro-vascular stent with a modified ANSI head phantom were obtained from the average of many exposures taken with the high-resolution Micro-Angiographic Fluoroscope (MAF) and with a Flat Panel Detector (FPD). The square of the Fourier Transform of each averaged image, equivalent to the measured product of the system GMTF and the object function in spatial-frequency space, was then divided by the normalized noise power spectra (NNPS) for each respective system to obtain a task-specific generalized signal-to-noise ratio. A generalized measured relative object detectability (GM-ROD) was obtained by taking the ratio of the integral of the resulting expressions for each detector system to give an overall metric that enables a realistic systems comparison for the given detection task. Results: The GM-ROD provides comparison of relative performance of detector systems from actual measurements of the object function as imaged by those detector systems. This metric includes noise correlations and spatial frequencies relevant to the specific object. Additionally, the integration bounds for the GM-ROD can be selected to emphasis the higher frequency band of each detector if high-resolution image details are to be evaluated. Examples of this new metric are discussed with a comparison of the MAF to the FPD for neuro-vascular interventional imaging. Conclusion: The GM-ROD is a new direct-measured task-specific metric that can provide clinically relevant comparison of the relative performance of imaging systems. Supported by NIH Grant: 2R01EB002873 and an equipment grant from Toshiba Medical Systems Corporation.

  10. Hanford Site solid waste acceptance criteria

    SciTech Connect (OSTI)

    Ellefson, M.D.

    1998-07-01

    Order 5820.2A requires that each treatment, storage, and/or disposal facility (referred to in this document as TSD unit) that manages low-level or transuranic waste (including mixed waste and TSCA PCB waste) maintain waste acceptance criteria. These criteria must address the various requirements to operate the TSD unit in compliance with applicable safety and environmental requirements. This document sets forth the baseline criteria for acceptance of radioactive waste at TSD units operated by WMH. The criteria for each TSD unit have been established to ensure that waste accepted can be managed in a manner that is within the operating requirements of the unit, including environmental regulations, DOE Orders, permits, technical safety requirements, waste analysis plans, performance assessments, and other applicable requirements. Acceptance criteria apply to the following TSD units: the Low-Level Burial Grounds (LLBG) including both the nonregulated portions of the LLBG and trenches 31 and 34 of the 218-W-5 Burial Ground for mixed waste disposal; Central Waste Complex (CWC); Waste Receiving and Processing Facility (WRAP); and T Plant Complex. Waste from all generators, both from the Hanford Site and from offsite facilities, must comply with these criteria. Exceptions can be granted as provided in Section 1.6. Specific waste streams could have additional requirements based on the 1901 identified TSD pathway. These requirements are communicated in the Waste Specification Records (WSRds). The Hanford Site manages nonradioactive waste through direct shipments to offsite contractors. The waste acceptance requirements of the offsite TSD facility must be met for these nonradioactive wastes. This document does not address the acceptance requirements of these offsite facilities.

  11. Assessment B - Program Criteria | Department of Energy

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

    B - Program Criteria Assessment B - Program Criteria Microsoft Word - Assessment-B-ProgramCriteria (218.66 KB) More Documents & Publications ATTACHMENT A - CHECKLIST FOR SELF ...

  12. A review of proposed Glen Canyon Dam interim operating criteria

    SciTech Connect (OSTI)

    LaGory, K.; Hlohowskyj, I.; Tomasko, D.; Hayse, J.; Durham, L.

    1992-04-01

    Three sets of interim operating criteria for Glen Canyon Dam on the Colorado River have been proposed for the period of November 1991, to the completion of the record of decision for the Glen Canyon Dam environmental impact statement (about 1993). These criteria set specific limits on dam releases, including maximum and minimum flows, up-ramp and down-ramp rates, and maximum daily fluctuation. Under the proposed interim criteria, all of these parameters would be reduced relative to historical operating criteria to protect downstream natural resources, including sediment deposits, threatened and endangered fishes, trout, the aquatic food base, and riparian plant communities. The scientific bases of the three sets of proposed operating criteria are evaluated in the present report:(1) criteria proposed by the Research/Scientific Group, associated with the Glen Canyon Environmental Studies (GCES); (2) criteria proposed state and federal officials charged with managing downstream resources; and (3) test criteria imposed from July 1991, to November 1991. Data from Phase 1 of the GCES and other sources established that the targeted natural resources are affected by dam operations, but the specific interim criteria chosen were not supported by any existing studies. It is unlikely that irreversible changes to any of the resources would occur over the interim period if historical operating criteria remained in place. It is likely that adoption of any of the sets of proposed interim operating criteria would reduce the levels of sediment transport and erosion below Glen Canyon Dam; however, these interim criteria could result in some adverse effects, including the accumulation of debris at tributary mouths, a shift of new high-water-zone vegetation into more flood-prone areas, and further declines in vegetation in the old high water zone.

  13. FHR Generic Design Criteria

    SciTech Connect (OSTI)

    Flanagan, George F; Holcomb, David Eugene; Cetiner, Sacit M

    2012-06-01

    The purpose of this document is to provide an initial, focused reference to the safety characteristics of and a licensing approach for Fluoride-Salt-Cooled High-Temperature Reactors (FHRs). The document does not contain details of particular reactor designs nor does it attempt to identify or classify either design basis or beyond design basis accidents. Further, this document is an initial attempt by a small set of subject matter experts to document the safety and licensing characteristics of FHRs for a larger audience. The document is intended to help in setting the safety and licensing research, development, and demonstration path forward. Input from a wider audience, further technical developments, and additional study will be required to develop a consensus position on the safety and licensing characteristics of FHRs. This document begins with a brief overview of the attributes of FHRs and then a general description of their anticipated safety performance. Following this, an overview of the US nuclear power plant approval process is provided that includes both test and power reactors, as well as the role of safety standards in the approval process. The document next describes a General Design Criteria (GDC) - based approach to licensing an FHR and provides an initial draft set of FHR GDCs. The document concludes with a description of a path forward toward developing an FHR safety standard that can support both a test and power reactor licensing process.

  14. FHR Generic Design Criteria

    SciTech Connect (OSTI)

    Flanagan, G.F.; Holcomb, D.E.; Cetiner, S.M.

    2012-06-15

    The purpose of this document is to provide an initial, focused reference to the safety characteristics of and a licensing approach for Fluoride-Salt-Cooled High-Temperature Reactors (FHRs). The document does not contain details of particular reactor designs nor does it attempt to identify or classify either design basis or beyond design basis accidents. Further, this document is an initial attempt by a small set of subject matter experts to document the safety and licensing characteristics of FHRs for a larger audience. The document is intended to help in setting the safety and licensing research, development, and demonstration path forward. Input from a wider audience, further technical developments, and additional study will be required to develop a consensus position on the safety and licensing characteristics of FHRs. This document begins with a brief overview of the attributes of FHRs and then a general description of their anticipated safety performance. Following this, an overview of the US nuclear power plant approval process is provided that includes both test and power reactors, as well as the role of safety standards in the approval process. The document next describes a General Design Criteria (GDC)–based approach to licensing an FHR and provides an initial draft set of FHR GDCs. The document concludes with a description of a path forward toward developing an FHR safety standard that can support both a test and power reactor licensing process.

  15. EXPO Award Criteria - Hanford Site

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

    Award Criteria About Us Hanford Cultural Resources Charging Your Time Committee Members Contact Us Electronic Registration Form Exhibitor and Vendor Information EXPO 2016 Sponsors EXPO Award Criteria How to Get to TRAC Special Events What is EXPO Why Should I Participate in EXPO EXPO Award Criteria Email Email Page | Print Print Page | Text Increase Font Size Decrease Font Size WRPS won the awards for Most Interactive and Best Overall booth! WRPS won the awards for Most Interactive and Best

  16. FTCP Assessment Guidance and Criteria

    Broader source: Energy.gov [DOE]

    This document establishes the guidance and criteria for conducting internal and independent Federal Technical Capability Assessments within the Department. The requirements of this document are applicable to those organizations having safety responsibilities for defense nuclear facilities. This includes both headquarters and field organizations. Regardless of the type of assessment conducted, the objectives and criteria within this document are used as a basis for the assessment. Use of consistent objectives and criteria is necessary to establish baselines and to track and trend performance.

  17. Functional Area Criteria & Review Approach Documents

    Broader source: Energy.gov [DOE]

    CRADS provided on this page are provided as examples of functional area Objectives and Criteria used to evaluate how requirements are meet. They are only examples and should not be utilized as is. In accordance with DOE Standard 3006-2010, CRADs should be developed by team members to reflect the specifics of the proposed review (i.e., breadth and depth) as defined in the approved Plan of Action.

  18. Evaluation Criteria for PDIL Proposal

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

    Criteria for PDIL Proposal The selection/decision criteria used by the NCPV Business Development Team are the following: 1. Quality and Relevance of the Proposed Technical Plan (30%) * Technology impact with industry and likelihood of success. Demonstrated benefits of success to both the proposer and NREL to meet the DOE SunShot goals. * Proposed task descriptions and time line. Clear demonstration of entrance and exit strategies in the PDIL. * Extent to which the Proposer and NREL can rapidly

  19. Guidelines Establishing Criteria for Excluding Buildings from...

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

    by the Energy Policy Act of 2005 Guidelines Establishing Criteria for Excluding ... This document contains the Guidelines Establishing Criteria for Excluding Buildings from ...

  20. Membership Criteria: Better Buildings Residential Network | Department...

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

    Membership Criteria: Better Buildings Residential Network of the U.S. Department of Energy. Membership Criteria (126.27 KB) More Documents & Publications Better Buildings ...

  1. Reportable Nuclide Criteria for ORNL Waste Management Activities - 13005

    SciTech Connect (OSTI)

    McDowell, Kip; Forrester, Tim; Saunders, Mark Edward

    2013-01-01

    The U.S. Department of Energy's Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee generates numerous radioactive waste streams. Many of those streams contain a large number of radionuclides with an extremely broad range of concentrations. To feasibly manage the radionuclide information, ORNL developed a reportable nuclide criteria to distinguish between those nuclides in a waste stream that require waste tracking versus those nuclides of such minimal activity that do not require tracking. The criteria include tracking thresholds drawn from ORNL onsite management requirements, transportation requirements, and relevant treatment and disposal facility acceptance criteria. As a management practice, ORNL maintains waste tracking on a nuclide in a specific waste stream if it exceeds any of the reportable nuclide criteria. Nuclides in a specific waste stream that screen out as non-reportable under all these criteria may be dropped from ORNL waste tracking. The benefit of this criteria is to ensure that nuclides in a waste stream with activities which meaningfully affect safety and compliance are tracked, while documenting the basis for removing certain isotopes from further consideration.

  2. Reportable Nuclide Criteria for ORNL Radioactive Waste Management Activities - 13005

    SciTech Connect (OSTI)

    McDowell, Kip; Forrester, Tim; Saunders, Mark

    2013-07-01

    The U.S. Department of Energy's Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee generates numerous radioactive waste streams. Many of those streams contain a large number of radionuclides with an extremely broad range of concentrations. To feasibly manage the radionuclide information, ORNL developed reportable nuclide criteria to distinguish between those nuclides in a waste stream that require waste tracking versus those nuclides of such minimal activity that do not require tracking. The criteria include tracking thresholds drawn from ORNL onsite management requirements, transportation requirements, and relevant treatment and disposal facility acceptance criteria. As a management practice, ORNL maintains waste tracking on a nuclide in a specific waste stream if it exceeds any of the reportable nuclide criteria. Nuclides in a specific waste stream that screen out as non-reportable under all these criteria may be dropped from ORNL waste tracking. The benefit of these criteria is to ensure that nuclides in a waste stream with activities which meaningfully affect safety and compliance are tracked, while documenting the basis for removing certain isotopes from further consideration. (authors)

  3. Criteria Review and Approach Documents | Department of Energy

    Energy Savers [EERE]

    Criteria Review and Approach Documents Criteria Review and Approach Documents CRAD Type Criteria Review and Approach Document List...

  4. Criteria and Review Approach Documents | Department of Energy

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

    Criteria and Review Approach Documents Criteria and Review Approach Documents CRAD Type Criteria and Review Approach Document List

  5. NWTS program criteria for mined geologic disposal of nuclear waste: program objectives, functional requirements, and system performance criteria

    SciTech Connect (OSTI)

    1981-04-01

    At the present time, final repository criteria have not been issued by the responsible agencies. This document describes general objectives, requirements, and criteria that the DOE intends to apply in the interim to the National Waste Terminal Storage (NWTS) Program. These objectives, requirements, and criteria have been developed on the basis of DOE's analysis of what is needed to achieve the National objective of safe waste disposal in an environmentally acceptable and economic manner and are expected to be consistent with anticipated regulatory standards. The qualitative statements in this document address the broad issues of public and occupational health and safety, institutional acceptability, engineering feasibility, and economic considerations. A comprehensive set of criteria, general and project specific, of which these are a part, will constitute a portion of the technical basis for preparation and submittal by the DOE of formal documents to support future license applications for nuclear waste repositories.

  6. Nuclear Safety Reporting Criteria | Department of Energy

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

    Reporting Criteria Nuclear Safety Reporting Criteria January 1, 2012 Nuclear Safety Noncompliances Associated With Occurrences (DOE Order 232.2) These tables provide the criteria for reporting nuclear safety noncompliances into the Department of Energy's Noncompliance Tracking System (NTS). A more detailed description of the NTS reporting criteria and expectations can be found in the Office of Health, Safety and Security's Enforcement Coordinator Handbook. Nuclear Safety Reporting Criteria

  7. Miniaturized reaction vessel system, method for performing site-specific biochemical reactions and affinity fractionation for use in DNA sequencing

    DOE Patents [OSTI]

    Mirzabekov, Andrei Darievich; Lysov, Yuri Petrovich; Dubley, Svetlana A.

    2000-01-01

    A method for fractionating and sequencing DNA via affinity interaction is provided comprising contacting cleaved DNA to a first array of oligonucleotide molecules to facilitate hybridization between said cleaved DNA and the molecules; extracting the hybridized DNA from the molecules; contacting said extracted hybridized DNA with a second array of oligonucleotide molecules, wherein the oligonucleotide molecules in the second array have specified base sequences that are complementary to said extracted hybridized DNA; and attaching labeled DNA to the second array of oligonucleotide molecules, wherein the labeled re-hybridized DNA have sequences that are complementary to the oligomers. The invention further provides a method for performing multi-step conversions of the chemical structure of compounds comprising supplying an array of polyacrylamide vessels separated by hydrophobic surfaces; immobilizing a plurality of reactants, such as enzymes, in the vessels so that each vessel contains one reactant; contacting the compounds to each of the vessels in a predetermined sequence and for a sufficient time to convert the compounds to a desired state; and isolating the converted compounds from said array.

  8. Nuclear Reactor Safety Design Criteria

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

    1993-01-19

    The order establishes nuclear safety criteria applicable to the design, fabrication, construction, testing, and performance requirements of nuclear reactor facilities and safety class structures, systems, and components (SSCs) within these facilities. Cancels paragraphs 8a and 8b of DOE 5480.6. Cancels DOE O 5480.6 in part. Supersedes DOE 5480.1, dated 1-19-93. Certified 11-18-10.

  9. Waste Specification Records - Hanford Site

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

    Specification Records About Us Hanford Site Solid Waste Acceptance Program What's New Acceptance Criteria Acceptance Process Becoming a new Hanford Customer Annual Waste Forecast and Funding Arrangements Waste Stream Approval Waste Shipment Approval Waste Receipt Quality Assurance Program Waste Specification Records Tools Points of Contact Waste Specification Records Email Email Page | Print Print Page | Text Increase Font Size Decrease Font Size Waste Specification Records (WSRds) are the tool

  10. A method for the assessment of site-specific economic impacts of commercial and industrial biomass energy facilities. A handbook and computer model

    SciTech Connect (OSTI)

    Not Available

    1994-10-01

    A handbook on ``A Method for the Assessment of Site-specific Econoomic Impacts of Industrial and Commercial Biomass Energy Facilities`` has been prepared by Resource Systems Group Inc. under contract to the Southeastern Regional Biomass Energy Program (SERBEP). The handbook includes a user-friendly Lotus 123 spreadsheet which calculates the economic impacts of biomass energy facilities. The analysis uses a hybrid approach, combining direct site-specific data provided by the user, with indirect impact multipliers from the US Forest Service IMPLAN input/output model for each state. Direct economic impacts are determined primarily from site-specific data and indirect impacts are determined from the IMPLAN multipliers. The economic impacts are given in terms of income, employment, and state and federal taxes generated directly by the specific facility and by the indirect economic activity associated with each project. A worksheet is provided which guides the user in identifying and entering the appropriate financial data on the plant to be evaluated. The WLAN multipliers for each state are included in a database within the program. The multipliers are applied automatically after the user has entered the site-specific data and the state in which the facility is located. Output from the analysis includes a summary of direct and indirect income, employment and taxes. Case studies of large and small wood energy facilities and an ethanol plant are provided as examples to demonstrate the method. Although the handbook and program are intended for use by those with no previous experience in economic impact analysis, suggestions are given for the more experienced user who may wish to modify the analysis techniques.

  11. 1999 EV America Technical Specifications

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

    9 EV AMERICA TECHNICAL SPECIFICATIONS Effective October 1, 1999 Prepared by Electric Transportation Applications 1999 EV AMERICA TECHNICAL SPECIFICATIONS 2 MINIMUM VEHICLE REQUIREMENTS For a vehicle to be considered qualified as an EV America-USDOE "Production" level vehicle, it must meet the minimum criteria defined by "shall" terminology utilized in the Specification. [For clarity, the use of the word "Shall" defines minimum requirements, whereas the use of the

  12. Idaho CERCLA Disposal Facility Complex Waste Acceptance Criteria

    SciTech Connect (OSTI)

    W. Mahlon Heileson

    2006-10-01

    The Idaho Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Disposal Facility (ICDF) has been designed to accept CERCLA waste generated within the Idaho National Laboratory. Hazardous, mixed, low-level, and Toxic Substance Control Act waste will be accepted for disposal at the ICDF. The purpose of this document is to provide criteria for the quantities of radioactive and/or hazardous constituents allowable in waste streams designated for disposal at ICDF. This ICDF Complex Waste Acceptance Criteria is divided into four section: (1) ICDF Complex; (2) Landfill; (3) Evaporation Pond: and (4) Staging, Storage, Sizing, and Treatment Facility (SSSTF). The ICDF Complex section contains the compliance details, which are the same for all areas of the ICDF. Corresponding sections contain details specific to the landfill, evaporation pond, and the SSSTF. This document specifies chemical and radiological constituent acceptance criteria for waste that will be disposed of at ICDF. Compliance with the requirements of this document ensures protection of human health and the environment, including the Snake River Plain Aquifer. Waste placed in the ICDF landfill and evaporation pond must not cause groundwater in the Snake River Plain Aquifer to exceed maximum contaminant levels, a hazard index of 1, or 10-4 cumulative risk levels. The defined waste acceptance criteria concentrations are compared to the design inventory concentrations. The purpose of this comparison is to show that there is an acceptable uncertainty margin based on the actual constituent concentrations anticipated for disposal at the ICDF. Implementation of this Waste Acceptance Criteria document will ensure compliance with the Final Report of Decision for the Idaho Nuclear Technology and Engineering Center, Operable Unit 3-13. For waste to be received, it must meet the waste acceptance criteria for the specific disposal/treatment unit (on-Site or off-Site) for which it is destined.

  13. CRAD, Specific Administrative Controls - December 14, 2007 | Department of

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

    Energy Specific Administrative Controls - December 14, 2007 CRAD, Specific Administrative Controls - December 14, 2007 December 14, 2007 Specific Administrative Controls Implementation Inspection Criteria, Approach, and Lines of Inquiry (HSS CRAD 64-32) This Criteria Review and Approach Document (HSS CRAD 64-32) establishes review criteria and lines of inquiry used by the Office of Independent Oversight's Office of Environment, Safety and Health Evaluations to assess the effectiveness of

  14. Rapid and sensitive gas chromatography ion-trap mass spectrometry method for the determination of tobacco specific N-nitrosamines in secondhand smoke

    SciTech Connect (OSTI)

    SLEIMAN, Mohamad; MADDALENA, Randy L.; GUNDEL, Lara A.; DESTAILLATS, Hugo

    2009-07-01

    Tobacco-specific nitrosamines (TSNAs) are some of the most potent carcinogens in tobacco and cigarette smoke. Accurate quantification of these chemicals is needed to help assess public health risks. We developed and validated a specific and sensitive method to measure four TSNAs in both the gas- and particle-phase of secondhand smoke (SHS) using gas chromatography and ion-trap tandem mass spectrometry,. A smoking machine in an 18-m3 room-sized chamber generated relevant concentrations of SHS that were actively sampled on Teflon coated fiber glass (TCFG) filters, and passively sampled on cellulose substrates. A simple solid-liquid extraction protocol using methanol as solvent was successfully applied to both filters with high recoveries ranging from 85 to 115percent. Tandem MS parameters were optimized to obtain the best sensitivity in terms of signal to-noise ratio (S/N) for the target compounds. For each TSNA, the major fragmentation pathways as well as ion structures were elucidated and compared with previously published data. The method showed excellent performances with a linear dynamic range between 2 and 1000 ng mL-1, low detection limits (S/N> 3) of 30-300 pg.ml-1 and precision with experimental errors below 10percent for all compounds. Moreover, no interfering peaks were observed indicating a high selectivity of MS/MS without the need for a sample clean up step. The sampling and analysis method provides a sensitive and accurate tool to detect and quantify traces of TSNA in SHS polluted indoor environments.

  15. Protocol, Inspection Criteria - April 23, 2008 | Department of...

    Energy Savers [EERE]

    Protocol, Inspection Criteria - April 23, 2008 Protocol, Inspection Criteria - April 23, 2008 April 23, 2008 Inspection Criteria, Activities, and Lines of Inquiry, April 23, 2008...

  16. Interim performance criteria for photovoltaic energy systems. [Glossary included

    SciTech Connect (OSTI)

    DeBlasio, R.; Forman, S.; Hogan, S.; Nuss, G.; Post, H.; Ross, R.; Schafft, H.

    1980-12-01

    This document is a response to the Photovoltaic Research, Development, and Demonstration Act of 1978 (P.L. 95-590) which required the generation of performance criteria for photovoltaic energy systems. Since the document is evolutionary and will be updated, the term interim is used. More than 50 experts in the photovoltaic field have contributed in the writing and review of the 179 performance criteria listed in this document. The performance criteria address characteristics of present-day photovoltaic systems that are of interest to manufacturers, government agencies, purchasers, and all others interested in various aspects of photovoltaic system performance and safety. The performance criteria apply to the system as a whole and to its possible subsystems: array, power conditioning, monitor and control, storage, cabling, and power distribution. They are further categorized according to the following performance attributes: electrical, thermal, mechanical/structural, safety, durability/reliability, installation/operation/maintenance, and building/site. Each criterion contains a statement of expected performance (nonprescriptive), a method of evaluation, and a commentary with further information or justification. Over 50 references for background information are also given. A glossary with definitions relevant to photovoltaic systems and a section on test methods are presented in the appendices. Twenty test methods are included to measure performance characteristics of the subsystem elements. These test methods and other parts of the document will be expanded or revised as future experience and needs dictate.

  17. Technical Qualification Program Accreditation Objectives and Criteria |

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

    Department of Energy Objectives and Criteria Technical Qualification Program Accreditation Objectives and Criteria The program clearly identifies and documents the process used to demonstrate employee technical competence. TQP Accreditation Objectives and Criteria (40.57 KB) More Documents & Publications Technical Qualification Program Self-Assessment Report - Sandia Site Office - 2012 Technical Qualification Program Self-Assessment Report - Richland Operations Office - 2014 Technical

  18. Accuracy-based time step criteria for solving parabolic equations

    SciTech Connect (OSTI)

    Mohtar, R.; Segerlind, L.

    1995-12-31

    Parabolic equations govern many transient engineering problems. Space integration using finite element or finite difference methods changes the parabolic partial differential equation into an ordinary differential equation. Time integration schemes are needed to solve the later equation. In order to accurately perform the later integration a proper time step must be provided. Time step estimates based on a stability criteria have been prescribed in the literature. The following paper presents time step estimates that satisfy stability as well as accuracy criteria. These estimates were correlated to the Froude and Courant Numbers. The later criteria were found to be overly conservative for some integration schemes. Suggestions as to which time integration scheme is the best to use are also presented.

  19. Anticipating Potential Waste Acceptance Criteria for Defense Spent Nuclear Fuel

    SciTech Connect (OSTI)

    Rechard, R.P.; Lord, M.E.; Stockman, C.T.; McCurley, R.D.

    1997-12-31

    The Office of Environmental Management of the U.S. Department of Energy is responsible for the safe management and disposal of DOE owned defense spent nuclear fuel and high level waste (DSNF/DHLW). A desirable option, direct disposal of the waste in the potential repository at Yucca Mountain, depends on the final waste acceptance criteria, which will be set by DOE`s Office of Civilian Radioactive Waste Management (OCRWM). However, evolving regulations make it difficult to determine what the final acceptance criteria will be. A method of anticipating waste acceptance criteria is to gain an understanding of the DOE owned waste types and their behavior in a disposal system through a performance assessment and contrast such behavior with characteristics of commercial spent fuel. Preliminary results from such an analysis indicate that releases of 99Tc and 237Np from commercial spent fuel exceed those of the DSNF/DHLW; thus, if commercial spent fuel can meet the waste acceptance criteria, then DSNF can also meet the criteria. In large part, these results are caused by the small percentage of total activity of the DSNF in the repository (1.5%) and regulatory mass (4%), and also because commercial fuel cladding was assumed to provide no protection.

  20. Security Enforcement Reporting Criteria | Department of Energy

    Office of Environmental Management (EM)

    Mandatory Security Incident Reporting This document provides information and criteria for reporting classified information security incidents and noncompliances to the Department ...

  1. Nevada National Security Site Waste Acceptance Criteria

    National Nuclear Security Administration (NNSA)

    Nevada National Security Site Waste Acceptance Criteria Prepared by U.S. Department of Energy National Nuclear Security Administration Nevada Field Office Environmental...

  2. Vermont Small Hydropower Assistance Program Screening Criteria...

    Open Energy Info (EERE)

    LibraryAdd to library PermittingRegulatory Guidance - GuideHandbook: Vermont Small Hydropower Assistance Program Screening Criteria Summary and Application InstructionsPermitting...

  3. Range Design Criteria- June 4, 2012

    Broader source: Energy.gov [DOE]

    This document contains the currently-approved firearms "Range Design Criteria" referred to on DOE O 473.3, Protection Program Operations

  4. WPN 99-7- WAP Eligibility Criteria

    Broader source: Energy.gov [DOE]

    To provide states with guidance on the interpretation of certain eligibility criteria for use in the low-income Weatherization Assistance Program.

  5. Electronic Records Management Software Applications Design Criteria...

    Energy Savers [EERE]

    Electronic Records Management Software Applications Design Criteria Standard This Standard is reissued under the authority of DoD Directive 5015.2, "Department of DefenseRecords ...

  6. Example Procedures for Developing Acceptance-Range Criteria for BESTEST-EX

    SciTech Connect (OSTI)

    Ron Judkoff, Ben Polly, Marcus Bianchi

    2010-08-01

    This document provides an example procedure for establishing acceptance-range criteria to assess results from software undergoing BESTEST-EX. This example method for BESTEST-EX is a modified version of the method described in HERS BESTEST.

  7. TRU waste acceptance criteria for the Waste Isolation Pilot Plant: Revision 3

    SciTech Connect (OSTI)

    Not Available

    1989-01-01

    This document is intended to delineate the criteria by which unclassified waste will be accepted for emplacement at the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico and describe the bases upon which these criteria were established. These criteria are not intended to be specifications but rather limits that will allow waste generating and shipping sites to develop their own procedures and specifications for preparation of TRU waste for shipment to the WIPP. These criteria will also allow waste generating sites to plan future facilities for waste preparation that will produce TRU waste forms compatible with WIPP waste emplacement and isolation requirements. These criteria only apply to contract-handled (CH) and remote-handled (RH) transuranic (TRU) waste forms and are not intended to apply to beta-gamma wastes, spent fuel, high-level waste (HLW), low-level waste (LLW), low specific activity (LSA) waste, or forms of radioactive waste for experimental purposes. Specifications for receipt of experimental waste forms will be prepared by the responsible projects in conjunction with the staff of the WIPP project at a later date. In addition, these criteria only apply to waste emplaced in bedded rock salt. Technical bases for these criteria may differ significantly from those for other host rocks. 25 refs. 4 figs., 1 tab.

  8. Guide to nondestructive assay standards: Preparation criteria, availability, and practical considerations

    SciTech Connect (OSTI)

    Stewart, J.E.; Hsue, S.T.; Sampson, T.E.

    1997-10-01

    For certification and measurement control, nondestructive assay (NDA) instruments and methods used for verification measurement of special nuclear materials (SNMs) require calibrations based on certified reference materials (CRMs), or working reference materials (WRMs), traceable to the national system of measurements, and adequately characteristic of the unknowns. The Department of Energy Office of Safeguards and Security is sponsoring production of a comprehensive guide to preparation of NDA standards. The scope of the report includes preparation criteria, current availability of CRMs and WRMs, practical considerations for preparation and characterization, and an extensive bibliography. In preparing the report, based primarily on experience at Los Alamos, we have found that standards preparation is highly dependent on the particular NDA method being applied. We therefore include sections that contain information specific to commonly used neutron and gamma-ray NDA techniques. 16 refs., 4 figs., 2 tabs.

  9. Guide to nondestructive assay standards: Preparation criteria, availability, and practical considerations

    SciTech Connect (OSTI)

    Hsue, S.T.; Stewart, J.E.; Sampson, T.E.; Butler, G.W.; Rudy, C.R.; Rinard, P.M.

    1997-10-01

    For certification and measurement control, nondestructive assay (NDA) instruments and methods used for verification measurements of special nuclear materials (SNMs) require calibrations based on certified reference materials (CRMs), or working reference materials (WRMs), traceable to the national system of measurements, and adequately characteristic of the unknowns. The Department of Energy Office of Safeguards and Security is sponsoring production of a comprehensive guide to preparation of NDA standards. The scope of the report includes preparation criteria, current availability of CRMs and WRMs, practical considerations for preparation and characterization, and an extensive bibliography. In preparing the report, based primarily on experience at Los Alamos, they have found that standards preparation is highly dependent on the particular NDA method being applied. They therefore include sections that contain information specific to commonly used neutron and gamma-ray NDA techniques. They also present approaches that are alternatives to, or minimize requirements for physical standards.

  10. APPLICATION OF COLUMN EXTRACTION METHOD FOR IMPURITIES ANALYSIS ON HB-LINE PLUTONIUM OXIDE IN SUPPORT OF MOX FEED PRODUCT SPECIFICATIONS

    SciTech Connect (OSTI)

    Jones, M.; Diprete, D.; Wiedenman, B.

    2012-03-20

    The current mission at H-Canyon involves the dissolution of an Alternate Feedstocks 2 (AFS-2) inventory that contains plutonium metal. Once dissolved, HB-Line is tasked with purifying the plutonium solution via anion exchange, precipitating the Pu as oxalate, and calcining to form plutonium oxide (PuO{sub 2}). The PuO{sub 2} will provide feed product for the Mixed Oxide (MOX) Fuel Fabrication Facility, and the anion exchange raffinate will be transferred to H-Canyon. The results presented in this report document the potential success of the RE resin column extraction application on highly concentrated Pu samples to meet MOX feed product specifications. The original 'Hearts Cut' sample required a 10000x dilution to limit instrument drift on the ICP-MS method. The instrument dilution factors improved to 125x and 250x for the sample raffinate and sample eluent, respectively. As noted in the introduction, the significantly lower dilutions help to drop the total MRL for the analyte. Although the spike recoveries were half of expected in the eluent for several key elements, they were between 94-98% after Nd tracer correction. It is seen that the lower ICD limit requirements for the rare earths are attainable because of less dilution. Especially important is the extremely low Ga limit at 0.12 {mu}g/g Pu; an ICP-MS method is now available to accomplish this task on the sample raffinate. While B and V meet the column A limits, further development is needed to meet the column B limits. Even though V remained on the RE resin column, an analysis method is ready for investigation on the ICP-MS, but it does not mean that V cannot be measured on the ICP-ES at a low dilution to meet the column B limits. Furthermore, this column method can be applicable for ICP-ES as shown in Table 3-2, in that it trims the sample of Pu, decreasing and sometimes eliminating Pu spectral interferences.

  11. Program Evaluation: Criteria, Logistics, Cost, and Analysis | Department of

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

    Energy Criteria, Logistics, Cost, and Analysis Program Evaluation: Criteria, Logistics, Cost, and Analysis There are a few criteria that are often recommended and used by the DOE, OMB, NAS, and others. Although programs may choose to define additional criteria, at a minimum all EERE programs are expected to use the following three criteria (referred to as "core criteria"). The three core criteria are the following: Quality, Productivity, and Accomplishments. Quality, as used here,

  12. Commissioning Specifications

    Office of Energy Efficiency and Renewable Energy (EERE)

    Commissioning specifications outline basic requirements of the commissioning process and detail the roles and responsibilities of each party involved. System checklists, startup requirements, and...

  13. Generalized Lawson Criteria for Inertial Confinement Fusion

    SciTech Connect (OSTI)

    Tipton, Robert E.

    2015-08-27

    The Lawson Criterion was proposed by John D. Lawson in 1955 as a general measure of the conditions necessary for a magnetic fusion device to reach thermonuclear ignition. Over the years, similar ignition criteria have been proposed which would be suitable for Inertial Confinement Fusion (ICF) designs. This paper will compare and contrast several ICF ignition criteria based on Lawson’s original ideas. Both analytical and numerical results will be presented which will demonstrate that although the various criteria differ in some details, they are closely related and perform similarly as ignition criteria. A simple approximation will also be presented which allows the inference of each ignition parameter directly from the measured data taken on most shots fired at the National Ignition Facility (NIF) with a minimum reliance on computer simulations. Evidence will be presented which indicates that the experimentally inferred ignition parameters on the best NIF shots are very close to the ignition threshold.

  14. Facility Representative Program, Criteria & Review Approach Documents

    Office of Energy Efficiency and Renewable Energy (EERE)

    This page provides Criteria Review and Approach Documents (CRADS) to assist Facility Representatives. Please submit your CRADS for posting by sending them to the HQ FR Program Manager. Please include the subject, date, and a contact person.

  15. Natural phenomena hazards site characterization criteria

    SciTech Connect (OSTI)

    Not Available

    1994-03-01

    The criteria and recommendations in this standard shall apply to site characterization for the purpose of mitigating Natural Phenomena Hazards (wind, floods, landslide, earthquake, volcano, etc.) in all DOE facilities covered by DOE Order 5480.28. Criteria for site characterization not related to NPH are not included unless necessary for clarification. General and detailed site characterization requirements are provided in areas of meteorology, hydrology, geology, seismology, and geotechnical studies.

  16. Electronic Records Management Software Applications Design Criteria

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

    Standard | Department of Energy Electronic Records Management Software Applications Design Criteria Standard Electronic Records Management Software Applications Design Criteria Standard This Standard is reissued under the authority of DoD Directive 5015.2, "Department of DefenseRecords Management Program," March 6, 2000, (Reference (a)) which provides implementing and procedural guidance on the management of records in the Department of Defense. Electronic Records Management

  17. Criteria for SES Positions | Department of Energy

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

    Services » Executive Resources » Senior Executive Service (SES) » Criteria for SES Positions Criteria for SES Positions Initial career appointments to the SES must be made following competitive merit staffing requirements. Agencies must announce SES vacancies that will be filled by initial career appointment to at least all Federal civil service employees. Vacancies are published on the USAJOBS Veteran's preference does not apply to SES selections. An Executive Resources Board (ERB) is

  18. Multi-criteria evaluation in strategic environmental assessment for waste management plan, a case study: The city of Belgrade

    SciTech Connect (OSTI)

    Josimović, Boško Marić, Igor; Milijić, Saša

    2015-02-15

    Highlights: • The paper deals with the specific method of multi-criteria evaluation applied in drafting the SEA for the Belgrade WMP. • MCE of the planning solutions, assessed according to 37 objectives of the SEA and four sets of criteria, was presented in the matrix form. • The results are presented in the form of graphs so as to be easily comprehensible to all the participants in the decision-making process. • The results represent concrete contribution proven in practice. - Abstract: Strategic Environmental Assessment (SEA) is one of the key instruments for implementing sustainable development strategies in planning in general; in addition to being used in sectoral planning, it can also be used in other areas such as waste management planning. SEA in waste management planning has become a tool for considering the benefits and consequences of the proposed changes in space, also taking into account the capacity of space to sustain the implementation of the planned activities. In order to envisage both the positive and negative implications of a waste management plan for the elements of sustainable development, an adequate methodological approach to evaluating the potential impacts must be adopted and the evaluation results presented in a simple and clear way, so as to allow planners to make relevant decisions as a precondition for the sustainability of the activities planned in the waste management sector. This paper examines the multi-criteria evaluation method for carrying out an SEA for the Waste Management Plan for the city of Belgrade (BWMP). The method was applied to the evaluation of the impacts of the activities planned in the waste management sector on the basis of the environmental and socioeconomic indicators of sustainability, taking into consideration the intensity, spatial extent, probability and frequency of impact, by means of a specific planning approach and simple and clear presentation of the obtained results.

  19. A new approach to criteria for health risk assessment

    SciTech Connect (OSTI)

    Spickett, Jeffery; Katscherian, Dianne; Goh, Yang Miang

    2012-01-15

    Health Impact Assessment (HIA) is a developing component of the overall impact assessment process and as such needs access to procedures that can enable more consistent approaches to the stepwise process that is now generally accepted in both EIA and HIA. The guidelines developed during this project provide a structured process, based on risk assessment procedures which use consequences and likelihood, as a way of ranking risks to adverse health outcomes from activities subjected to HIA or HIA as part of EIA. The aim is to assess the potential for both acute and chronic health outcomes. The consequences component also identifies a series of consequences for the health care system, depicted as expressions of financial expenditure and the capacity of the health system. These more specific health risk assessment characteristics should provide for a broader consideration of health consequences and a more consistent estimation of the adverse health risks of a proposed development at both the scoping and risk assessment stages of the HIA process. - Highlights: Black-Right-Pointing-Pointer A more objective approach to health risk assessment is provided. Black-Right-Pointing-Pointer An objective set of criteria for the consequences for chronic and acute impacts. Black-Right-Pointing-Pointer An objective set of criteria for the consequences on the health care system. Black-Right-Pointing-Pointer An objective set of criteria for event frequency that could impact on health. Black-Right-Pointing-Pointer The approach presented is currently being trialled in Australia.

  20. MERGING CRITERIA FOR GIANT IMPACTS OF PROTOPLANETS

    SciTech Connect (OSTI)

    Genda, H.; Kokubo, E.; Ida, S.

    2012-01-10

    At the final stage of terrestrial planet formation, known as the giant impact stage, a few tens of Mars-sized protoplanets collide with one another to form terrestrial planets. Almost all previous studies on the orbital and accretional evolution of protoplanets in this stage have been based on the assumption of perfect accretion, where two colliding protoplanets always merge. However, recent impact simulations have shown that collisions among protoplanets are not always merging events, that is, two colliding protoplanets sometimes move apart after the collision (hit-and-run collision). As a first step toward studying the effects of such imperfect accretion of protoplanets on terrestrial planet formation, we investigated the merging criteria for collisions of rocky protoplanets. Using the smoothed particle hydrodynamic method, we performed more than 1000 simulations of giant impacts with various parameter sets, such as the mass ratio of protoplanets, {gamma}, the total mass of two protoplanets, M{sub T}, the impact angle, {theta}, and the impact velocity, v{sub imp}. We investigated the critical impact velocity, v{sub cr}, at the transition between merging and hit-and-run collisions. We found that the normalized critical impact velocity, v{sub cr}/v{sub esc}, depends on {gamma} and {theta}, but does not depend on M{sub T}, where v{sub esc} is the two-body escape velocity. We derived a simple formula for v{sub cr}/v{sub esc} as a function of {gamma} and {theta} (Equation (16)), and applied it to the giant impact events obtained by N-body calculations in the previous studies. We found that 40% of these events should not be merging events.

  1. DOE Standard: Fire protection design criteria

    SciTech Connect (OSTI)

    Not Available

    1999-07-01

    The development of this Standard reflects the fact that national consensus standards and other design criteria do not comprehensively or, in some cases, adequately address fire protection issues at DOE facilities. This Standard provides supplemental fire protection guidance applicable to the design and construction of DOE facilities and site features (such as water distribution systems) that are also provided for fire protection. It is intended to be used in conjunction with the applicable building code, National Fire Protection Association (NFPA) Codes and Standards, and any other applicable DOE construction criteria. This Standard replaces certain mandatory fire protection requirements that were formerly in DOE 5480.7A, ``Fire Protection``, and DOE 6430.1A, ``General Design Criteria``. It also contains the fire protection guidelines from two (now canceled) draft standards: ``Glove Box Fire Protection`` and ``Filter Plenum Fire Protection``. (Note: This Standard does not supersede the requirements of DOE 5480.7A and DOE 6430.1A where these DOE Orders are currently applicable under existing contracts.) This Standard, along with the criteria delineated in Section 3, constitutes the basic criteria for satisfying DOE fire and life safety objectives for the design and construction or renovation of DOE facilities.

  2. Understanding seismic design criteria for Japanese nuclear power...

    Office of Scientific and Technical Information (OSTI)

    Understanding seismic design criteria for Japanese nuclear power plants Citation Details In-Document Search Title: Understanding seismic design criteria for Japanese nuclear power ...

  3. Energy Department Announces More Stringent Criteria for ENERGY...

    Office of Environmental Management (EM)

    More Stringent Criteria for ENERGY STAR Refrigerators Energy Department Announces More Stringent Criteria for ENERGY STAR Refrigerators August 3, 2007 - 2:55pm Addthis ...

  4. Criteria and Guidelines for the Federal Energy and Water Management...

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

    Criteria and Guidelines for the Federal Energy and Water Management Awards Criteria and Guidelines for the Federal Energy and Water Management Awards Document outlines the 2016 ...

  5. Worker Safety and Health Reporting Criteria | Department of Energy

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

    Worker Safety and Health Reporting Criteria Worker Safety and Health Reporting Criteria January 1, 2012 Worker Safety and Health Noncompliances Associated With Occurrences(DOE ...

  6. A review of macroscopic ductile failure criteria. (Technical...

    Office of Scientific and Technical Information (OSTI)

    Technical Report: A review of macroscopic ductile failure criteria. Citation Details In-Document Search Title: A review of macroscopic ductile failure criteria. The objective of ...

  7. Statistical criteria for characterizing irradiance time series.

    SciTech Connect (OSTI)

    Stein, Joshua S.; Ellis, Abraham; Hansen, Clifford W.

    2010-10-01

    We propose and examine several statistical criteria for characterizing time series of solar irradiance. Time series of irradiance are used in analyses that seek to quantify the performance of photovoltaic (PV) power systems over time. Time series of irradiance are either measured or are simulated using models. Simulations of irradiance are often calibrated to or generated from statistics for observed irradiance and simulations are validated by comparing the simulation output to the observed irradiance. Criteria used in this comparison should derive from the context of the analyses in which the simulated irradiance is to be used. We examine three statistics that characterize time series and their use as criteria for comparing time series. We demonstrate these statistics using observed irradiance data recorded in August 2007 in Las Vegas, Nevada, and in June 2009 in Albuquerque, New Mexico.

  8. Aseismic design criteria for uranium enrichment plants

    SciTech Connect (OSTI)

    Beavers, J.E.

    1980-01-01

    In this paper technological, economical, and safety issues of aseismic design of uranium enrichment plants are presented. The role of management in the decision making process surrounding these issues is also discussed. The resolution of the issues and the decisions made by management are controlling factors in developing aseismic design criteria for any facility. Based on past experience in developing aseismic design criteria for the GCEP various recommendations are made for future enrichment facilities, and since uranium enrichment plants are members of the nuclear fuel cycle the discussion and recommendations presented herein are applicable to other nonreactor nuclear facilities.

  9. Solid waste disposal facility criteria. Technical manual

    SciTech Connect (OSTI)

    Not Available

    1993-11-01

    The technical manual has been developed to assist municipal solid waste landfill (MSWLF) owners and operators in achieving compliance with the revised MSWLF Criteria, promulgated on October 9, 1991 in Title 40, Part 258, of the Code of Federal Regulations (CFR). The manual is not a regulatory document, and does not provide mandatory technical guidance, but does provide assistance for coming into compliance with the technical aspects of the revised landfill Criteria. The document is intended for use by landfill owners/operators and their consultants and contractors who provide advice on demonstrating compliance with the Part 258 standards.

  10. Hanford Site Solid Waste Acceptance Criteria

    SciTech Connect (OSTI)

    Not Available

    1993-11-17

    This manual defines the Hanford Site radioactive, hazardous, and sanitary solid waste acceptance criteria. Criteria in the manual represent a guide for meeting state and federal regulations; DOE Orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to acceptance of radioactive and hazardous solid waste at the Hanford Site. It is not the intent of this manual to be all inclusive of the regulations; rather, it is intended that the manual provide the waste generator with only the requirements that waste must meet in order to be accepted at Hanford Site TSD facilities.

  11. History and Evolution of the Johnson Criteria.

    SciTech Connect (OSTI)

    Sjaardema, Tracy A.; Smith, Collin S.; Birch, Gabriel Carisle

    2015-07-01

    The Johnson Criteria metric calculates probability of detection of an object imaged by an optical system, and was created in 1958 by John Johnson. As understanding of target detection has improved, detection models have evolved to better model additional factors such as weather, scene content, and object placement. The initial Johnson Criteria, while sufficient for technology and understanding at the time, does not accurately reflect current research into target acquisition and technology. Even though current research shows a dependence on human factors, there appears to be a lack of testing and modeling of human variability.

  12. Nevada Test Site Waste Acceptance Criteria

    SciTech Connect (OSTI)

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

    2005-10-01

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive (LLW) and mixed waste (MW) for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex (RWMC) for storage or disposal.

  13. NEVADA TEST SITE WASTE ACCEPTANCE CRITERIA

    SciTech Connect (OSTI)

    U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION, NEVADA SITE OFFICE

    2005-07-01

    This document establishes the U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive and mixed waste for disposal. Mixed waste generated within the State of Nevada by NNSA/NSO activities is accepted for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Site for storage or disposal.

  14. Nevada Test Site Waste Acceptance Criteria (NTSWAC)

    SciTech Connect (OSTI)

    NNSA /NSO Waste Management Project

    2008-06-01

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive (LLW) and LLW Mixed Waste (MW) for disposal.

  15. IHE material qualification tests description and criteria

    SciTech Connect (OSTI)

    Slape, R J

    1984-06-01

    This report describes the qualification tests presently being used at Pantex Plant, Lawrence Livermore National Laboratory, and Los Alamos National Laboratory that are required by the Department of Energy prior to the approval for an explosive as an Insensitive High Explosive (IHE) material. The acceptance criteria of each test for IHE qualification is also discussed. 5 references, 10 figures.

  16. Membership Criteria: Better Buildings Residential Network | Department of

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

    Energy Membership Criteria: Better Buildings Residential Network Membership Criteria: Better Buildings Residential Network Membership Criteria: Better Buildings Residential Network of the U.S. Department of Energy. Membership Criteria (126.27 KB) More Documents & Publications Better Buildings Residential Network Orientation Better Buildings Residential Network Reporting and Benefits FAQ How Can the Network Meet Your Needs?

  17. CRAD, Safety Systems Inspection Criteria- December 17, 2012

    Office of Energy Efficiency and Renewable Energy (EERE)

    Safety Systems Inspection Criteria in implementing Integrated Safety Management, (HSS CRAD 45-11, Rev. 3)

  18. Packaging design criteria for the MCO cask

    SciTech Connect (OSTI)

    Edwards, W.S.

    1996-04-29

    Approximately 2,100 metric tons of unprocessed, irradiated nuclear fuel elements are presently stored in the K Basins (including possibly 700 additional elements from PUREX, N Reactor, and 327 Laboratory). The basin water, particularly in the K East Basin, contains significant quantities of dissolved nuclear isotopes and radioactive fuel corrosion particles. To permit cleanup of the K Basins and fuel conditioning, the fuel will be transported from the 100 K Area to a Canister Storage Building (CSB) in the 200 East area. In order to initiate K Basin cleanup on schedule, the two-year fuel-shipping campaign must begin by December 1997. The purpose of this packaging design criteria is to provide criteria for the design, fabrication, and use of a packaging system to transport the large quantities of irradiated nuclear fuel elements positioned within Multiple Canister Overpacks.

  19. Nevada National Security Site Waste Acceptance Criteria

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2011-01-01

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NNSSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NNSS Area 3 and Area 5 Radioactive Waste Management Complex for disposal. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project at (702) 295-7063 or fax to (702) 295-1153.

  20. Nevada National Security Site Waste Acceptance Criteria

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2010-09-03

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NNSSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NNSS Area 3 and Area 5 Radioactive Waste Management Complex for disposal. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project at (702) 295-7063 or fax to (702) 295-1153.

  1. Microsoft Word - Assessment-B-ProgramCriteria

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

    ATTACHMENT B PROGRAM ASSESSMENT CRITERIA Identify the following for all sites: Program Management * Number FTE's devoted to Records Management o Full-time Federal and Contractor o Part-time Federal and Contractor Percent of time spent on Records Management duties * Percentage of time each Records Management employee is assigned to: o Program Management o Operations Training/Assistance Schedule Application Records Holding/Storage Area Activities EEOICPA Claims * Monthly Claim Volume Other,

  2. Application Content and Evaluation Criteria/Process

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

    Evaluation Criteria/Process Jill Gruber Golden Field Office Department of Energy May 18, 2007 The information presented here is an outline of how the Funding Opportunity Announcement (FOA) may be structured. The final application requirements will be shown in the FOA when it is posted on Grants.gov. The schedule and awards are dependent on future appropriations and may change if future appropriations are lower than expected or in the event of a continuing resolution. DOE Points of Contact DOE

  3. Application Content and Evaluation Criteria/Process

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

    Evaluation Criteria/Process Reginald Tyler Golden Field Office Office of Hydrogen, Fuel Cells and Infrastructure Technologies Application Content o Separate Applications for Each Major Topic o Title Should Identify the Topic Area o Application - SF 424 o Budget File - SF 424A o Project Summary - 1 page, non-proprietary Project Narrative o Provide clear description of the technical concept and how you plan to accomplish the work. o Include a description of the relevance of and justification for

  4. Proposal Writing Guidelines and Scoring Criteria

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

    Proposal Writing Guidelines and Scoring Criteria Print Principal Investigator The proposal form asks for the names and contact information of the experiment leader completing the form and the Principal Investigator (PI). The PI is the leader and the individual responsible for the group, and the experiment leader is often the person completing the proposal form. In this way the ALS would like to encourage postdocs and students to gain experience in submitting proposals as the experiment leader,

  5. Qualitative methods for assessing risk

    SciTech Connect (OSTI)

    Mahn, J.A.; Hannaman, G.W.; Kryska, P.

    1995-04-01

    The Department of Energy`s (DOE) non-nuclear facilities generally require only a qualitative accident analysis to assess facility risks in accordance with DOE Order 5481.1B, Safety Analysis and Review System. Achieving a meaningful qualitative assessment of risk necessarily requires the use of suitable non-numerical assessment criteria. Typically, the methods and criteria for assigning facility-specific accident scenarios to the qualitative severity and likelihood classification system in the DOE order requires significant judgment in many applications. Systematic methods for more consistently assigning the total accident scenario frequency and associated consequences are required to substantiate and enhance future risk ranking between various activities at Sandia National Laboratories (SNL). SNL`s Risk Management and National Environmental Policy Act (NEPA) Department has developed an improved methodology for performing qualitative risk assessments in accordance wi the DOE order requirements. Products of this effort are an improved set of qualitative description that permit (1) definition of the severity for both technical and programmatic consequences that may result from a variety of accident scenarios, and (2) qualitative representation of the likelihood of occurrence. These sets of descriptions are intended to facilitate proper application of DOE criteria for assessing facility risks.

  6. Acceptance Criteria Framework for Autonomous Biological Detectors

    SciTech Connect (OSTI)

    Dzenitis, J M

    2006-12-12

    The purpose of this study was to examine a set of user acceptance criteria for autonomous biological detection systems for application in high-traffic, public facilities. The test case for the acceptance criteria was the Autonomous Pathogen Detection System (APDS) operating in high-traffic facilities in New York City (NYC). However, the acceptance criteria were designed to be generally applicable to other biological detection systems in other locations. For such detection systems, ''users'' will include local authorities (e.g., facility operators, public health officials, and law enforcement personnel) and national authorities [including personnel from the Department of Homeland Security (DHS), the BioWatch Program, the Centers for Disease Control and Prevention (CDC), and the Federal Bureau of Investigation (FBI)]. The panel members brought expertise from a broad range of backgrounds to complete this picture. The goals of this document are: (1) To serve as informal guidance for users in considering the benefits and costs of these systems. (2) To serve as informal guidance for developers in understanding the needs of users. In follow-up work, this framework will be used to systematically document the APDS for appropriateness and readiness for use in NYC.

  7. Harmonization of Biodiesel Specifications

    SciTech Connect (OSTI)

    Alleman, T. L.

    2008-02-01

    Worldwide biodiesel production has grown dramatically over the last several years. Biodiesel standards vary across countries and regions, and there is a call for harmonization. For harmonization to become a reality, standards have to be adapted to cover all feedstocks. Additionally, all feedstocks cannot meet all specifications, so harmonization will require standards to either tighten or relax. For harmonization to succeed, the biodiesel market must be expanded with the alignment of test methods and specification limits, not contracted.

  8. Machine plumbness criteria: Interim technology release

    SciTech Connect (OSTI)

    Not Available

    1987-06-01

    The objective of this technology release is to define the maximum allowable deviation from plumb of the centrifuge machine and to recommend machine installation techniques to achieve the specified criteria. The centrifuge feature used as a reference for plumbness is the casing centerline as defined by a line drawn between the theoretical centers of the top and bottom flange faces. In practice, this measurement is accomplished by using specified casing flange diameters or bolt patterns as the reference points. The criterion adopted for GCEP is that each machine shall be plumb within 0.5 in. over the length of the casing as initially installed. Over a long period of time the plumbness is allowed to degrade to 1.0 in. This standard should be achievable using the currently planned installation techniques and within a time limit consistent with GCEP operational objectives. For development testing, centrifuge machines are meticulously adjusted using a plumb bob to achieve a plumbness with 1/8 in. About one to two days are required to complete the installation. This level of effort is justified for a development machine especially where baseline data is being gathered. A more reasonable standard with a corresponding reduction in installation time is required for GCEP. The specified criteria of 0.5 in. maximum out-of-plumb at time of installation and 1.0 in., ultimate, are believed to be a reasonable compromise. Machine design features or operating modes that are dependent on vertical alignment were examined to assess the impact of the selected plumbness criteria. Machine performance and design requirements are defined in the applicable technology release documents.

  9. Project X functional requirements specification

    SciTech Connect (OSTI)

    Holmes, S.D.; Henderson, S.D.; Kephart, R.; Kerby, J.; Kourbanis, I.; Lebedev, V.; Mishra, S.; Nagaitsev, S.; Solyak, N.; Tschirhart, R.; /Fermilab

    2012-05-01

    Project X is a multi-megawatt proton facility being developed to support a world-leading program in Intensity Frontier physics at Fermilab. The facility is designed to support programs in elementary particle and nuclear physics, with possible applications to nuclear energy research. A Functional Requirements Specification has been developed in order to establish performance criteria for the Project X complex in support of these multiple missions, and to assure that the facility is designed with sufficient upgrade capability to provide U.S. leadership for many decades to come. This paper will briefly review the previously described Functional Requirements, and then discuss their recent evolution.

  10. 309 Facility deactivation and decommisioning Criteria Completion Check Lists

    SciTech Connect (OSTI)

    Cornwell, B.C.

    1996-02-01

    To facilitate and track completion of the 309 Facility turnover criteria completion an Applicability Matrix and Criteria Completion Check Lists were prepared. The applicability matrix documents the required turnover criteria for a given area in the facility or scope of work. The applicable criteria is selected for 16 different areas. For each area a completion checklist is provided to document completion of a requirement by WHC and the Environmental Restoration Contractor.

  11. Bioenergy and Food Security Criteria and Indicators (BEFSCI)...

    Open Energy Info (EERE)

    URI: cleanenergysolutions.orgcontentbioenergy-and-food-security-criteria- Language: English Policies: Deployment Programs DeploymentPrograms: Technical Assistance This...

  12. DOE Standard 1020 - Natural Phenomena Hazard analysis and Design Criteria

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

    for DOE Facilities | Department of Energy Standard 1020 - Natural Phenomena Hazard analysis and Design Criteria for DOE Facilities DOE Standard 1020 - Natural Phenomena Hazard analysis and Design Criteria for DOE Facilities Department of Energy (DOE) Standard (STD)-1020-2012, Natural Phenomena Hazards Analysis and Design Criteria for DOE Facilities, provides criteria and guidance for the analysis and design of facility structures, systems, and components (SSCs) that are necessary to

  13. FRACTURE FAILURE CRITERIA OF SOFC PEN STRUCTURE

    SciTech Connect (OSTI)

    Liu, Wenning N.; Sun, Xin; Khaleel, Mohammad A.; Qu, Jianmin

    2007-04-30

    Thermal stresses and warpage of the PEN are unavoidable due to the temperature changes from the stress-free sintering temperature to room temperature and mismatch of the coefficients of thermal expansion (CTE) of various layers in the PEN structures of solid oxide fuel cells (SOFC) during the PEN manufacturing process. In the meantime, additional mechanical stresses will also be created by mechanical flattening during the stack assembly process. The porous nature of anode and cathode in the PEN structures determines presence of the initial flaws and crack on the interfaces of anode/electrolyte/cathode and in the interior of the materials. The sintering/assembling induced stresses may cause the fracture failure of PEN structure. Therefore, fracture failure criteria for SOFC PEN structures is developed in order to ensure the structural integrity of the cell and stack of SOFC. In this paper, the fracture criteria based on the relationship between the critical energy release rate and critical curvature and maximum displacement of the warped cells caused by the temperature changes as well as mechanical flattening process is established so that possible failure of SOFC PEN structures may be predicted deterministically by the measurement of the curvature and displacement of the warped cells.

  14. Nevada National Security Site Waste Acceptance Criteria

    SciTech Connect (OSTI)

    none,

    2013-06-01

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept the following: • DOE hazardous and non-hazardous non-radioactive classified waste • DOE low-level radioactive waste (LLW) • DOE mixed low-level waste (MLLW) • U.S. Department of Defense (DOD) classified waste The LLW and MLLW listed above may also be classified waste. Classified waste is the only waste accepted for disposal that may be non-radioactive and shall be required to meet the waste acceptance criteria for radioactive waste as specified in this document. Classified waste may be sent to the NNSS as classified matter. Section 3.1.18 provides the requirements that must be met for permanent burial of classified matter. The NNSA/NFO and support contractors are available to assist the generator in understanding or interpreting this document. For assistance, please call the NNSA/NFO Environmental Management Operations (EMO) at (702) 295-7063, and the call will be directed to the appropriate contact.

  15. Nevada National Security Site Waste Acceptance Criteria

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2012-02-28

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept DOE non-radioactive classified waste, DOE non-radioactive hazardous classified waste, DOE low-level radioactive waste (LLW), DOE mixed low-level waste (MLLW), and U.S. Department of Defense (DOD) classified waste for permanent disposal. Classified waste is the only waste accepted for disposal that may be non-radioactive and will be required to meet the waste acceptance criteria for radioactive waste as specified in this document. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project (WMP) at (702) 295-7063, and your call will be directed to the appropriate contact.

  16. Criteria and Processes for the Certification of Non-Radioactive Hazardous and Non-Hazardous Wastes

    SciTech Connect (OSTI)

    Dominick, J

    2008-12-18

    Hazardous Waste Management (RHWM) organization is responsible for the review and maintenance of this document. It should be noted that the DOE metal recycling moratorium is still in effect and is implemented as outlined in reference 17 when metals are being dispositioned for disposal/re-use/recycling off-site. This document follows the same methodology as described in the previously approved 1992 Moratorium document. Generator knowledge and certification are the primary means of characterization. Sampling and analysis are used when there is insufficient knowledge of a waste to determine if it contains added radioactivity. Table 1 (page 12) presents a list of LLNL's analytical methods for evaluating volumetrically contaminated waste and updates the reasonably achievable analytical-method-specific Minimum Detectable Concentrations (MDCs) for various matrices. Results from sampling and analysis are compared against the maximum MDCs for the given analytical method and the sample specific MDC to determine if the sample contains DOE added volumetric radioactivity. The evaluation of an item that has a physical form, and history of use, such that accessible surfaces may be potentially contaminated, is based on DOE Order 5400.5 (Reference 3), and its associated implementation guidance document DOE G 441.1-XX, Control and Release of Property with Residual Radioactive Material (Reference 4). The guidance document was made available for use via DOE Memorandum (Reference 5). Waste and materials containing residual radioactivity transferred off-site must meet the receiving facilities Waste Acceptance Criteria (if applicable) and be in compliance with other applicable federal or state requirements.

  17. Impact of structural design criteria on first wall surface heat flux limit

    SciTech Connect (OSTI)

    Majumdar, S.

    1998-09-01

    The irradiation environment experienced by the in-vessel components of fusion reactors presents structural design challenges not envisioned in the development of existing structural design criteria such as the ASME Code or RCC-MR. From the standpoint of design criteria, the most significant issues stem from the irradiation-induced changes in material properties, specifically the reduction of ductility, strain hardening capability, and fracture toughness with neutron irradiation. Recently, Draft 7 of the ITER structural design criteria (ISDC), which provide new rules for guarding against such problems, was released for trial use by the ITER designers. The new rules, which were derived from a simple model based on the concept of elastic follow up factor, provide primary and secondary stress limits as functions of uniform elongation and ductility. The implication of these rules on the allowable surface heat flux on typical first walls made of type 316 stainless steel and vanadium alloys are discussed.

  18. An evaluation of Department of Transportation specification packages

    SciTech Connect (OSTI)

    Ratledge, J.E.; Rawl, R.R.

    1992-01-01

    Specification packages are broad families of package designs developed and authorized by the US Department of Transportation (DOT) and the Nuclear Regulatory Commission (NRC) for transport of certain Type B and fissile radioactive materials, with each specification containing a number of designs of various sizes. The specification package designs have remained essentially unchanged in a changing regulatory environment. Changes to package designs or authorized contents under the DOT system can be accomplished by rule making action, but there has been little updating of the designs over the years. Many of the individual package designs are no longer supported by reasonably current safety analyses. Since the publication of these specifications, there have been changes in regulatory requirements and improvements in methods of testing and analysis. Additionally, contemplated revisions to the DOT and NRC regulations to bring design requirements into accord with IAEA Safety Series No. 6, 1985 Edition would eliminate fissile classes and require resistance to a crush test for small Type B packages meeting certain criteria. The NRC has requested that the Oak Ridge National Laboratory (ORNL) staff review the safety documentation of the specification packages to determine the possible need for further testing and analysis, modifications to the designs, and, perhaps, elimination of any designs for which there is insufficient demonstration of compliance with current and proposed requirements. This paper will present a summary of the technical data and information concerning the use of the packages that has been received to date.

  19. An evaluation of Department of Transportation specification packages

    SciTech Connect (OSTI)

    Ratledge, J.E.; Rawl, R.R.

    1992-11-01

    Specification packages are broad families of package designs developed and authorized by the US Department of Transportation (DOT) and the Nuclear Regulatory Commission (NRC) for transport of certain Type B and fissile radioactive materials, with each specification containing a number of designs of various sizes. The specification package designs have remained essentially unchanged in a changing regulatory environment. Changes to package designs or authorized contents under the DOT system can be accomplished by rule making action, but there has been little updating of the designs over the years. Many of the individual package designs are no longer supported by reasonably current safety analyses. Since the publication of these specifications, there have been changes in regulatory requirements and improvements in methods of testing and analysis. Additionally, contemplated revisions to the DOT and NRC regulations to bring design requirements into accord with IAEA Safety Series No. 6, 1985 Edition would eliminate fissile classes and require resistance to a crush test for small Type B packages meeting certain criteria. The NRC has requested that the Oak Ridge National Laboratory (ORNL) staff review the safety documentation of the specification packages to determine the possible need for further testing and analysis, modifications to the designs, and, perhaps, elimination of any designs for which there is insufficient demonstration of compliance with current and proposed requirements. This paper will present a summary of the technical data and information concerning the use of the packages that has been received to date.

  20. Technical guidance for siting criteria development

    SciTech Connect (OSTI)

    Aldrich, D.C.; Sprung, J.L.; Alpert, D.J.; Diegert, K.; Ostmeyer, R.M.; Ritchie, L.T.; Strip, D.R.; Johnson, J.D.; Hansen, K.; Robinson, J.

    1982-12-01

    Technical guidance to support the formulation and comparison of possible siting criteria for nuclear power plants has been developed in four areas: (1) consequences of hypothetical severe nuclear-power-plant accidents, (2) characteristics of population distributions about current reactor sites, (3) site availability within the continental United States, and (4) socioeconomic impacts of reactor siting. The impact on consequences of source-term magnitude, meteorology, population distribution, and emergency response have been analyzed. Population distributions about current sites were analyzed to identify statistical characteristics, time trends, and regional differences. A site-availability data bank was constructed for the continential United States. The data bank contains information about population densities, seismicity, topography, water availability, and land-use restrictions. Finally, the socioeconomic impacts of rural-industrialization projects, energy boomtowns, and nuclear power plants were examined to determine their nature, magnitude, and dependence on site demography and remoteness.

  1. A review of macroscopic ductile failure criteria.

    SciTech Connect (OSTI)

    Corona, Edmundo; Reedlunn, Benjamin

    2013-09-01

    The objective of this work was to describe several of the ductile failure criteria com- monly used to solve practical problems. The following failure models were considered: equivalent plastic strain, equivalent plastic strain in tension, maximum shear, Mohr- Coulomb, Wellman's tearing parameter, Johnson-Cook and BCJ MEM. The document presents the main characteristics of each failure model as well as sample failure predic- tions for simple proportional loading stress histories in three dimensions and in plane stress. Plasticity calculations prior to failure were conducted with a simple, linear hardening, J2 plasticity model. The resulting failure envelopes were plotted in prin- cipal stress space and plastic strain space, where the dependence on stress triaxiality and Lode angle are clearly visible. This information may help analysts select a ductile fracture model for a practical problem and help interpret analysis results.

  2. Use of Multiple Criteria to Map the High-Temperature Scuffing Behaviorof Co-Based Superalloys

    SciTech Connect (OSTI)

    Blau, Peter Julian; YaoPhD, Matthew; Qu, Jun; WuPhD, James

    2009-01-01

    The goal of thisworkwas to rank, as quantitatively as possible, the high-temperature scuffing characteristics of a series of Co-based materials, including coatings, for possible use inwear-critical components like those in diesel engine exhaust systems and emission-controls. A cylinder pivoting on its side against a flat tilewas used as the testing geometry. All testswere performed at 600 C in air. The time-dependent torque response was recorded for each 60 min test to investigate trends in friction as surfaces roughened and debris deposits built up. Candidate materials included Stellite 6B, Pleuco 33 (a white cast iron), nitrided stainless steel Type 310, IDM 5399 (a high-silicon, molybdenum iron), and coatings of both Tribaloy T-400 and Stellite 3 on stainless steel. Measurements of the damaged areas on the scuffed tiles were used to calculate a specific normal load and plot it versus the roughness of the worn tiles to map experimental results in a way that indicated the severity of scuffing for each material combination. Data on the map were annotated to reflect visual observations of the extent of damage as well. Using this test method and the foregoing criteria, nitrided type 310 stainless steel against T-400 gave the best overall performance.

  3. Energy Department Announces More Stringent Criteria for ENERGY STAR®

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

    Refrigerators | Department of Energy Stringent Criteria for ENERGY STAR® Refrigerators Energy Department Announces More Stringent Criteria for ENERGY STAR® Refrigerators August 3, 2007 - 2:55pm Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced increased energy efficient criteria for refrigerators carrying the ENERGY STAR® label. In order to qualify, full-size refrigerators must be a minimum of 20 percent more efficient than current federal energy efficiency

  4. Facility Energy Management Guidelines and Criteria for Energy and Water

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

    Evaluations in Covered Facilities | Department of Energy Facility Energy Management Guidelines and Criteria for Energy and Water Evaluations in Covered Facilities Facility Energy Management Guidelines and Criteria for Energy and Water Evaluations in Covered Facilities Guidelines and criteria describe meeting requirements within Section 432 of the Energy Independence and Security Act of 2007 (EISA 2007), including defining facilities covered by the provision, designating facility energy

  5. Department of Energy Announces More Stringent Energy Efficient Criteria for

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

    ENERGY STAR® Dishwashers | Department of Energy Stringent Energy Efficient Criteria for ENERGY STAR® Dishwashers Department of Energy Announces More Stringent Energy Efficient Criteria for ENERGY STAR® Dishwashers March 2, 2006 - 11:39am Addthis More Efficient Dishwashers Estimated to Save Consumers over $26 Million Annually WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced more stringent energy efficient criteria for dishwashers carrying the ENERGY STAR® label that

  6. Suppression criteria of parasitic mode oscillations in a gyrotron beam tunnel

    SciTech Connect (OSTI)

    Kumar, Nitin; Singh, Udaybir; Sinha, A. K.; Singh, T. P.

    2011-02-15

    This paper presents the design criteria of the parasitic mode oscillations suppression for a periodic, ceramic, and copper loaded gyrotron beam tunnel. In such a type of beam tunnel, the suppression of parasitic mode oscillations is an important design problem. A method of beam-wave coupling coefficient and its mathematical formulation are presented. The developed design criteria are used in the beam tunnel design of a 42 GHz gyrotron to be developed for the Indian TOKAMAK system. The role of the thickness and the radius of the beam tunnel copper rings to obtain the developed design criteria are also discussed. The commercially available electromagnetic code CST and the electron trajectory code EGUN are used for the simulations.

  7. The use of information technology security assessment criteria to protect specialized computer systems

    SciTech Connect (OSTI)

    Lykov, V.A.; Shein, A.V.; Piskarev, A.S.; Devaney, D.M.; Melton, R.B.; Hunteman, W.J.; Prommel, J.M.; Rothfuss, J.S.

    1997-10-01

    The purpose of this paper is to discuss the information security assessment criteria used in Russia and compare it with that used in the United States. The computer system security assessment criteria utilized by the State Technical Commission of Russia and similar criteria utilized by the US Department of Defense (TCSEC) are intended for the development and implementation of proven methods for achieving a required level of information security. These criteria are utilized, first and foremost, when conducting certification assessments of general purpose systems. The Russian Federation is creating specialized systems for nuclear material control and accountancy (MC and A) within the framework of the international laboratory-to-laboratory collaboration. Depending on the conditions in which the MC and A system is intended to operate, some of the criteria and the attendant certification requirements may exceed those established or may overlap the requirements established for attestation of such systems. In this regard it is possible to modify the certification and attestation requirements depending on the conditions in which a system will operate in order to achieve the ultimate goal--implementation of the systems in the industry.

  8. Criteria and Indicators for Sustainable Woodfuels | Open Energy...

    Open Energy Info (EERE)

    Type: Guidemanual Website: www.fao.orgdocrep012i1673ei1673e00.pdf Criteria and Indicators for Sustainable Woodfuels Screenshot References: Sustainable Woodfuels1...

  9. Facility Energy Management Guidelines and Criteria for Energy...

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

    Facility Energy Management Guidelines and Criteria for Energy and Water Evaluations in Covered Facilities (42 U.S.C. 8253 Subsection (f), Use of Energy and Water Efficiency ...

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

    Open Energy Info (EERE)

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

  11. Natural Phenomena Hazard Analysis and Design Criteria for Department...

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

    20-2012, Natural Phenomena Hazard Analysis and Design Criteria for Department of Energy Facilities by Diane Johnson This Department of Energy (DOE) Standard (STD)-1020-2012,...

  12. Vermont Agency of Commerce and Community Development's Criteria...

    Open Energy Info (EERE)

    case-by-case basis and focus on direct and indirect impacts of a substantial nature. Use of these criteria further implements any applicable state and federal review...

  13. Readiness Review Training- Development of Criteria And Review Approach Documents

    Broader source: Energy.gov [DOE]

    Slides used for November 8-9, 2010 Readiness Review Training - Development of Criteria And Review Approach Documents at the Idaho National Laboratory.

  14. CO - Floodplain Stormwater and Criteria Manual | Open Energy...

    Open Energy Info (EERE)

    This webpage provides the floodplain stormwater and criteria in Colorado. Author Colorado Water Conservation Board - Department of Natural Resources Published Colorado Water...

  15. Texas PUCT Substantive Rule 25.101, Certification Criteria, Electric...

    Open Energy Info (EERE)

    Help Apps Datasets Community Login | Sign Up Search Page Edit with form History Texas PUCT Substantive Rule 25.101, Certification Criteria, Electric Substantive Rules Jump...

  16. Facility Energy Management Guidelines and Criteria for Energy...

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

    for Energy and Water Evaluations in Covered Facilities Guidelines and criteria describe meeting requirements within Section 432 of the Energy Independence and Security Act of 2007 ...

  17. NITRATE DESTRUCTION LITERATURE SURVEY AND EVALUATION CRITERIA

    SciTech Connect (OSTI)

    Steimke, J.

    2011-02-01

    literature survey of technologies to perform the nitrate to hydroxide conversion, selection of the most promising technologies, preparation of a flowsheet and design of a system. The most promising technologies are electrochemical reduction of nitrates and chemical reduction with hydrogen or ammonia. The primary reviewed technologies are listed and they aredescribed in more detail later in the report: (1) Electrochemical destruction; (2) Chemical reduction with agents such as ammonia, hydrazine or hydrogen; (3) Hydrothermal reduction process; and (4) Calcination. Only three of the technologies on the list have been demonstrated to generate usable amounts of caustic; electrochemical reduction and chemical reduction with ammonia, hydrazine or hydrogen and hydrothermal reduction. Chemical reduction with an organic reactant such as formic acid generates carbon dioxide which reacts with caustic and is thus counterproductive. Treatment of nitrate with aluminum or other active metals generates a solid product. High temperature calcination has the potential to generate sodium oxide which may be hydrated to sodium hydroxide, but this is unproven. The following criteria were developed to evaluate the most suitable option. The numbers in brackets after the criteria are relative weighting factors to account for importance: (1) Personnel exposure to radiation for installation, routine operation and maintenance; (2) Non-radioactive safety issues; (3) Whether the technology generates caustic and how many moles of caustic are generated per mole of nitrate plus nitrite decomposed; (4) Whether the technology can handle nitrate and nitrite at the concentrations encountered in waste; (5) Maturity of technology; (6) Estimated annual cost of operation (labor, depreciation, materials, utilities); (7) Capital cost; (8) Selectivity to nitrogen as decomposition product (other products are flammable and/or toxic); (9) Impact of introduced species; (10) Selectivity for destruction of nitrate vs

  18. Analysis of the impact of safeguards criteria

    SciTech Connect (OSTI)

    Mullen, M.F.; Reardon, P.T.

    1981-01-01

    As part of the US Program of Technical Assistance to IAEA Safeguards, the Pacific Northwest Laboratory (PNL) was asked to assist in developing and demonstrating a model for assessing the impact of setting criteria for the application of IAEA safeguards. This report presents the results of PNL's work on the task. The report is in three parts. The first explains the technical approach and methodology. The second contains an example application of the methodology. The third presents the conclusions of the study. PNL used the model and computer programs developed as part of Task C.5 (Estimation of Inspection Efforts) of the Program of Technical Assistance. The example application of the methodology involves low-enriched uranium conversion and fuel fabrication facilities. The effects of variations in seven parameters are considered: false alarm probability, goal probability of detection, detection goal quantity, the plant operator's measurement capability, the inspector's variables measurement capability, the inspector's attributes measurement capability, and annual plant throughput. Among the key results and conclusions of the analysis are the following: the variables with the greatest impact on the probability of detection are the inspector's measurement capability, the goal quantity, and the throughput; the variables with the greatest impact on inspection costs are the throughput, the goal quantity, and the goal probability of detection; there are important interactions between variables. That is, the effects of a given variable often depends on the level or value of some other variable. With the methodology used in this study, these interactions can be quantitatively analyzed; reasonably good approximate prediction equations can be developed using the methodology described here.

  19. Module 5- EVMS Concepts and Methods

    Broader source: Energy.gov [DOE]

    This module outlines the criteria needed for implementing Earned Value management, the basic Earned Value terminology, and the different methods used to calculate Earned Value.

  20. Concepts and criteria for evaluating topsoil substitutes: The Texas experience

    SciTech Connect (OSTI)

    Askenasy, P.; Senkayi, A.L.; Joseph, W.L.

    1997-12-31

    Presented in this paper are: (1) historical background, (2) Federal and State regulatory basis and authority, and (3) justification for selected criteria and parameters which are currently used to evaluate the quality of topsoil-substitute materials and postmine soils in Texas. The specific parameters and concepts discussed include (1) acid- and toxic-forming materials (AFM and TFM), (2) quantification procedures for AFM and TFM, (3) procedures used to identify topsoil substitutes that are {open_quotes}equal to or more suitable than{close_quotes} existing premine native soils, and (4) current interpretations of what is meant by {open_quotes}the best available material to support revegetation{close_quotes} of surface-mined areas. To support these interpretations, reference is made throughout the paper to relevant sections of the (1) Texas Coal Mining Regulations (TCMR), (2) Surface Mining Control and Reclamation Act (SMCRA), and (3) Federal regulations promulgated by the Office of Surface Mining (OSM) to implement SMCRA. The success of the Texas reclamation program, as indicated by the quality of the reclaimed soils is also discussed. This success is partly attributed to the rigorous application of the quantification concepts and parameters discussed in this paper.

  1. Lubricant selection criteria and the tribological system

    SciTech Connect (OSTI)

    Lauer, D.A.

    1995-07-01

    Before the proper lubricant selection can be made, the tribological system must be identified to its fullest extent. This system includes the type of motion, speeds, temperatures, loads and the environment that is specific to the application. Once these parameters are identified, lubrication engineers or tribo-engineers can use their knowledge of the different lubricant chemistries to make a lubricant selection that will optimize the performance of the application. In addition to lubricant chemistry knowledge, the lubrication engineer also must analyze the application based on the identified tribological system. This analysis includes such topics as speed factors, elastohydrodynamic lubrication, extreme pressure lubrication, emergency lubrication and various special application requirements.

  2. Licensed reactor nuclear safety criteria applicable to DOE reactors

    SciTech Connect (OSTI)

    Not Available

    1993-11-01

    This document is a compilation and source list of nuclear safety criteria that the Nuclear Regulatory Commission (NRC) applies to licensed reactors; it can be used by DOE and DOE contractors to identify NRC criteria to be evaluated for application to the DOE reactors under their cognizance. The criteria listed are those that are applied to the areas of nuclear safety addressed in the safety analysis report of a licensed reactor. They are derived from federal regulations, USNRC regulatory guides, Standard Review Plan (SRP) branch technical positions and appendices, and industry codes and standards.

  3. Summary of the Advanced Reactor Design Criteria (ARDC) Phase 2 Activities

    SciTech Connect (OSTI)

    Holbrook, Mark Raymond

    2015-09-01

    This report provides an end-of-year summary reflecting the progress and status of proposed regulatory design criteria for advanced non-LWR designs in accordance with the Level 3 milestone in M3AT-15IN2001017 in work package AT-15IN200101. These criteria have been designated as ARDC, and they provide guidance to future applicants for addressing the GDC that are currently applied specifically to LWR designs. The report provides a summary of Phase 2 activities related to the various tasks associated with ARDC development and the subsequent development of example adaptations of ARDC for Sodium Fast Reactor (SFR) and modular High Temperature Gas-cooled Reactor (HTGR) designs.

  4. Double Shell Tank (DST) Utilities Specification

    SciTech Connect (OSTI)

    SUSIENE, W.T.

    2000-04-27

    This specification establishes the performance requirements and provides the references to the requisite codes and standards to he applied during the design of the Double-Shell Tank (DST) Utilities Subsystems that support the first phase of waste feed delivery (WFD). The DST Utilities Subsystems provide electrical power, raw/potable water, and service/instrument air to the equipment and structures used to transfer low-activity waste (LAW) and high-level waste (HLW) to designated DST staging tanks. The DST Utilities Subsystems also support the equipment and structures used to deliver blended LAW and HLW feed from these staging tanks to the River Protection Project (RPP) Privatization Contractor facility where the waste will be immobilized. This specification is intended to be the basis for new projects/installations. This specification is not intended to retroactively affect previously established project design criteria without specific direction by the program.

  5. Statistical Methods Handbook for Advanced Gas Reactor Fuel Materials

    SciTech Connect (OSTI)

    J. J. Einerson

    2005-05-01

    Fuel materials such as kernels, coated particles, and compacts are being manufactured for experiments simulating service in the next generation of high temperature gas reactors. These must meet predefined acceptance specifications. Many tests are performed for quality assurance, and many of these correspond to criteria that must be met with specified confidence, based on random samples. This report describes the statistical methods to be used. The properties of the tests are discussed, including the risk of false acceptance, the risk of false rejection, and the assumption of normality. Methods for calculating sample sizes are also described.

  6. U.S. NRC CONFIRMATORY LEVEL 1 PRA SUCCESS CRITERIA ACTIVITIES

    SciTech Connect (OSTI)

    Donald Helton; Hossein Esmaili; Robert Buell

    2011-03-01

    The U.S. Nuclear Regulatory Commission’s standardized plant analysis risk (SPAR) models are used to support a number of risk-informed initiatives. The fidelity and realism of these models are ensured through a number of processes including cross-comparison with industry models, review and use by a wide range of technical experts, and confirmatory analysis. This paper will describe a key activity in the latter arena. Specifically, this paper will describe MELCOR analyses performed to augment the technical basis for confirming or modifying specific success criteria of interest. The analyses that will be summarized provide the basis for confirming or changing success criteria in a specific 3-loop pressurized-water reactor and a Mark-I boiling-water reactor. Initiators that have been analyzed include loss-of-coolant accidents, loss of main feedwater, spontaneous steam generator tube rupture, inadvertent opening of a relief valve at power, and station blackout. For each initiator, specific aspects of the accident evolution are investigated via a targeted set of calculations (3 to 22 distinct accident analyses per initiator). Further evaluation is ongoing to extend the analyses’ conclusions to similar plants (where appropriate), with consideration of design and modeling differences on a scenario-by-scenario basis. This paper will also describe future plans.

  7. Department of Energy Announces Tougher Criteria for ENERGY STAR®...

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

    The Department of Energy projects that this new criteria could result in savings of over ... each year, equivalent to the amount of water that flows over Niagara Falls in four hours. ...

  8. Understanding seismic design criteria for Japanese Nuclear Power Plants

    SciTech Connect (OSTI)

    Park, Y.J.; Hofmayer, C.H.; Costello, J.F.

    1995-04-01

    This paper summarizes the results of recent survey studies on the seismic design practice for nuclear power plants in Japan. The seismic design codes and standards for both nuclear as well as non-nuclear structures have been reviewed and summarized. Some key documents for understanding Japanese seismic design criteria are also listed with brief descriptions. The paper highlights the design criteria to determine the seismic demand and component capacity in comparison with U.S. criteria, the background studies which have led to the current Japanese design criteria, and a survey of current research activities. More detailed technical descriptions are presented on the development of Japanese shear wall equations, design requirements for containment structures, and ductility requirements.

  9. Federal Energy and Water Management Awards Criteria Briefing Webinar

    Broader source: Energy.gov [DOE]

    Webinar provides an overview of the 2015 Federal Energy and Water Management Awards criteria and eligibility requirements, as well as tips on how to prepare nomination narratives to achieve better scores.

  10. Application Content and Evaluation Criteria/Process | Department...

    Office of Environmental Management (EM)

    Presentation on Application Content and Evaluation CriteriaProcess presented at the PEM fuel cell pre-solicitation meeting held May 26, 2005 in Arlington, VA. fcwrkshpreg.pdf ...

  11. DOE-STD-1066-99; Fire Protection Design Criteria

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

    ... Safety Analysis Report (SAR). 7.3.2 In the design of sway bracing, the criteria of Section 4-14.4.3.5.3 (or current equivalent) of NFPA 13 (1996) should be revised as follows. ...

  12. Criteria for Global Nuclear Energy Development

    SciTech Connect (OSTI)

    Lawrence, Michael J.

    2002-07-01

    Global energy consumption will at least double over the next fifty years due to population growth, increased consumption, and an urgent need to improve the standard of living in under-developed countries. Thirty percent of this growth will be for electricity. At the same time, carbon emissions must be significantly reduced to respond to concerns regarding global warming. The use of nuclear energy to meet this growing electricity demand without carbon emissions is an obvious solution to many observers, however real concerns over economics, safety, waste and proliferation must be adequately addressed. The issue is further complicated by the fact that developing countries, which have the most pressing need for additional electricity generation, have the least capability and infrastructure to deploy nuclear energy. Nevertheless, if the specific needs of developing countries are appropriately considered now as new generation reactors are being developed, and institutional arrangements based upon the fundamental principles of President Eisenhower's 1953 Atoms For Peace speech are followed, nuclear energy could be deployed in any country. From a technical perspective, reactor safety and accessibility of special nuclear material are primary concerns. Institutionally, plant and fuel ownership and waste management issues must be addressed. International safety and safeguards authority are prerequisites. While the IAEA's IMPRO program and the United States' Generation IV programs are focusing on technical solutions, institutional issues, particularly with regard to deployment in developing countries, are not receiving corresponding attention. Full-service, cradle-to-grave, nuclear electricity companies that retain custody and responsibility for the plant and materials, including waste, are one possible solution. Small modular reactors such as the Pebble Bed Modular Reactor could be ideal for such an arrangement. While waste disposal remains a major obstacle, this is already

  13. NWTS program criteria for mined geologic disposal of nuclear waste: repository performance and development criteria. Public draft

    SciTech Connect (OSTI)

    1982-07-01

    This document, DOE/NWTS-33(3) is one of a series of documents to establish the National Waste Terminal Storage (NWTS) program criteria for mined geologic disposal of high-level radioactive waste. For both repository performance and repository development it delineates the criteria for design performance, radiological safety, mining safety, long-term containment and isolation, operations, and decommissioning. The US Department of Energy will use these criteria to guide the development of repositories to assist in achieving performance and will reevaluate their use when the US Nuclear Regulatory Commission issues radioactive waste repository rules.

  14. Criteria for Evaluation of Nuclear Facility Training Programs

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

    Reaffirmed June 2013 DOE STANDARD CRITERIA FOR EVALUATION OF NUCLEAR FACILITY TRAINING PROGRAMS (Formerly Titled: Guidelines for Evaluation of Nuclear Facility Training Programs) U.S. Department of Energy FSC Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS DOE HDBK-1070-94 Errata June 2013 Table of Changes Page/Section Change Cover Criteria for Evaluation of Nuclear Facility Training Programs Page ii This document is available on the

  15. Los Alamos Waste Acceptance Criteria | Department of Energy

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

    Waste Acceptance Criteria Los Alamos Waste Acceptance Criteria This document was used to determine facts and conditions during the Department of Energy Accident Investigation Board's investigation into the radiological release event at the Waste Isolation Pilot Plant. Additional documents referenced and listed in the Phase 2 Radiological Release Event at the Waste Isolation Pilot Plant on February 14, 2014, report in Attachment F. Bibliography and References, are available on various public

  16. Entanglement criteria via concave-function uncertainty relations

    SciTech Connect (OSTI)

    Huang Yichen

    2010-07-15

    A general theorem as a necessary condition for the separability of quantum states in both finite and infinite dimensional systems, based on concave-function uncertainty relations, is derived. Two special cases of the general theorem are stronger than two known entanglement criteria based on the Shannon entropic uncertainty relation and the Landau-Pollak uncertainty relation, respectively; other special cases are able to detect entanglement where some famous entanglement criteria fail.

  17. Strain-Based Acceptance Criteria for Energy-Limited Events

    SciTech Connect (OSTI)

    Spencer D. Snow; Dana K. Morton

    2009-07-01

    The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code was primarily written with stress-based acceptance criteria. These criteria are applicable to force, displacement, and energy-controlled loadings and ensure a factor of safety against failure. However, stress-based acceptance criteria are often quite conservative for one time energy-limited events such as accidental drops and impacts. For several years, the ASME Working Group on Design of Division 3 Containments has been developing the Design Articles for Section III, Division 3, “Containments for Transportation and Storage of Spent Nuclear Fuel and High-Level Radioactive Material and Waste,” and has wanted to establish strain-based acceptance criteria for accidental drops of containments. This Division 3 working group asked the Working Group on Design Methodology (WGDM) to assist in developing these strain-based acceptance criteria. This paper discusses the current proposed strain-based acceptance criteria, associated limitations of use, its background development, and the current status.

  18. Solar Photovoltaic SPECIFICATION, CHECKLIST...

    Energy Savers [EERE]

    Ready Home SOLAR PHOTOVOLTAIC SPECIFICATION, CHECKLIST AND GUIDE i Table of Contents About the Renewable Energy Ready Home Specifications Assumptions of the RERH Solar ...

  19. Nonreactor Nuclear Safety Design Criteria and Explosive Safety Criteria Guide for Use with DOE O 420.1, Facility Safety

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

    2000-03-28

    This Guide provides guidance on the application of requirements for nonreactor nuclear facilities and explosives facilities of Department of Energy (DOE) O 420.1, Facility Safety, Section 4.1, Nuclear and Explosives Safety Design Criteria. No cancellation.

  20. Comparison of Test Procedures and Energy Efficiency Criteria in Selected International Standards and Labeling Programs for Clothes Washers, Water Dispensers, Vending Machines and CFLs

    SciTech Connect (OSTI)

    Fridley, David; Zheng, Nina; Zhou, Nan

    2010-06-01

    Since the late 1970s, energy labeling programs and mandatory energy performance standards have been used in many different countries to improve the efficiency levels of major residential and commercial equipment. As more countries and regions launch programs covering a greater range of products that are traded worldwide, greater attention has been given to harmonizing the specific efficiency criteria in these programs and the test methods for measurements. For example, an international compact fluorescent light (CFL) harmonization initiative was launched in 2006 to focus on collaboration between Australia, China, Europe and North America. Given the long history of standards and labeling programs, most major energy-consuming residential appliances and commercial equipment are already covered under minimum energy performance standards (MEPS) and/or energy labels. For these products, such as clothes washers and CFLs, harmonization may still be possible when national MEPS or labeling thresholds are revised. Greater opportunity for harmonization exists in newer energy-consuming products that are not commonly regulated but are under consideration for new standards and labeling programs. This may include commercial products such as water dispensers and vending machines, which are only covered by MEPS or energy labels in a few countries or regions. As China continues to expand its appliance standards and labeling programs and revise existing standards and labels, it is important to learn from recent international experiences with efficiency criteria and test procedures for the same products. Specifically, various types of standards and labeling programs already exist in North America, Europe and throughout Asia for products in China's 2010 standards and labeling programs, namely clothes washers, water dispensers, vending machines and CFLs. This report thus examines similarities and critical differences in energy efficiency values, test procedure specifications and other

  1. Application of multi-criteria decision-making on strategic municipal solid waste management in Dalmatia, Croatia

    SciTech Connect (OSTI)

    Vego, Goran Kucar-Dragicevic, Savka Koprivanac, Natalija

    2008-11-15

    The efficiency of providing a waste management system in the coastal part of Croatia consisting of four Dalmatian counties has been modelled. Two multi-criteria decision-making (MCDM) methods, PROMETHEE and GAIA, were applied to assist with the systematic analysis and evaluation of the alternatives. The analysis covered two levels; first, the potential number of waste management centres resulting from possible inter-county cooperation; and second, the relative merits of siting of waste management centres in the coastal or hinterland zone was evaluated. The problem was analysed according to several criteria; and ecological, economic, social and functional criteria sets were identified as relevant to the decision-making process. The PROMETHEE and GAIA methods were shown to be efficient tools for analysing the problem considered. Such an approach provided new insights to waste management planning at the strategic level, and gave a reason for rethinking some of the existing strategic waste management documents in Croatia.

  2. Guidance for Developing Principal Design Criteria for Advanced (Non-Light Water) Reactors

    SciTech Connect (OSTI)

    Holbrook, Mark; Kinsey, Jim

    2015-03-01

    In July 2013, the US Department of Energy (DOE) and US Nuclear Regulatory Commission (NRC) established a joint initiative to address a key portion of the licensing framework essential to advanced (non-light water) reactor technologies. The initiative addressed the “General Design Criteria for Nuclear Power Plants,” Appendix A to10 Code of Federal Regulations (CFR) 50, which were developed primarily for light water reactors (LWRs), specific to the needs of advanced reactor design and licensing. The need for General Design Criteria (GDC) clarifications in non-LWR applications has been consistently identified as a concern by the industry and varied stakeholders and was acknowledged by the NRC staff in their 2012 Report to Congress1 as an area for enhancement. The initiative to adapt GDC requirements for non-light water advanced reactor applications is being accomplished in two phases. Phase 1, managed by DOE, consisted of reviews, analyses and evaluations resulting in recommendations and deliverables to NRC as input for NRC staff development of regulatory guidance. Idaho National Laboratory (INL) developed this technical report using technical and reactor technology stakeholder inputs coupled with analysis and evaluations provided by a team of knowledgeable DOE national laboratory personnel with input from individual industry licensing consultants. The DOE national laboratory team reviewed six different classes of emerging commercial reactor technologies against 10 CFR 50 Appendix A GDC requirements and proposed guidance for their adapted use in non-LWR applications. The results of the Phase 1 analysis are contained in this report. A set of draft Advanced Reactor Design Criteria (ARDC) has been proposed for consideration by the NRC in the establishment of guidance for use by non-LWR designers and NRC staff. The proposed criteria were developed to preserve the underlying safety bases expressed by the original GDC, and recognizing that advanced reactors may take

  3. Development of design criteria for a high pressure vessel construction code

    SciTech Connect (OSTI)

    Mraz, G.J.

    1987-05-01

    Out of concern for public safety, most legal jurisdictions now require unfired pressure vessel construction to comply with the ASME Boiler and Pressure Vessel Code. Because the present two divisions of Section VIII of that Code are not well suited for high pressure design, a new division is needed. The currently anticipated main design criteria of the proposed division are full plastic flow or full overstrain pressure, stress intensity in the bore, fatigue, and fracture mechanics. The rules are expected to allow better utilization of high strength steels already included in the present Section VIII. At the same time materials of even higher strength are introduced. The benefits of compressive prestress are recognized. Construction methods allowing it's achievement, such as autofrettage, shrink fitting and wire winding are included. Reasons for selection of the criteria are given.

  4. DOE-STD-1023-95; Natural Phenomena Hazards Assessment Criteria

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

    ... Criteria for the atmospheric pressure change and recommended windborne missiles are ... pressure change (APC) and tornado missiles) need to be considered based on criteria ...

  5. Title 44 Part 60 Criteria for Land Management and Use | Open...

    Open Energy Info (EERE)

    Title 44 Part 60 Criteria for Land Management and UseLegal Abstract Sets forth the criteria by which the Federal Insurance Administrator will determine the adequacy...

  6. The Uniform Methods Project: Methods for Determining Energy Efficiency...

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

    The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures The Uniform Methods Project: Methods for Determining Energy Efficiency Savings...

  7. The Uniform Methods Project: Methods for Determining Energy Efficiency...

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

    The Uniform Methods Project: Methods for Determining Energy Efficiency Savings for Specific Measures (April 2013) The Uniform Methods Project: Methods for Determining Energy...

  8. Multi-criteria analysis on how to select solar radiation hydrogen production system

    SciTech Connect (OSTI)

    Badea, G.; Naghiu, G. S. Felseghi, R.-A.; Giurca, I.; Răboacă, S.; Aşchilean, I.

    2015-12-23

    The purpose of this article is to present a method of selecting hydrogen-production systems using the electric power obtained in photovoltaic systems, and as a selecting method, we suggest the use of the Advanced Multi-Criteria Analysis based on the FRISCO formula. According to the case study on how to select the solar radiation hydrogen production system, the most convenient alternative is the alternative A4, namely the technical solution involving a hydrogen production system based on the electrolysis of water vapor obtained with concentrated solar thermal systems and electrical power obtained using concentrating photovoltaic systems.

  9. Photovoltaic module certification/laboratory accreditation criteria development: Implementation handbook

    SciTech Connect (OSTI)

    Osterwald, C.R.; Hammond, R.L.; Wood, B.D.; Backus, C.E.; Sears, R.L.; Zerlaut, G.A.; D`Aiello, R.V.

    1996-08-01

    This document covers the second phase of a two-part program. Phase I provided an overview of the structure and function of typical product certification/laboratory accreditation programs. This report (Phase H) provides most of the draft documents that will be necessary for the implementation of a photovoltaic (PV) module certification/laboratory accreditation program. These include organizational documents such as articles of incorporation, bylaws, and rules of procedure, as well as marketing and educational program documents. In Phase I, a 30-member criteria development committee was established to guide, review and reach a majority consensus regarding criteria for a PV certification/laboratory accreditation program. Committee members represented PV manufacturers, end users, standards and codes organizations, and testing laboratories. A similar committee was established for Phase II; the criteria implementation committee consisted of 29 members. Twenty-one of the Phase I committee members also served on the Phase II committee, which helped to provide program continuity during Phase II.

  10. Data Quality Objectives for WTP Feed Acceptance Criteria - 12043

    SciTech Connect (OSTI)

    Arakali, Aruna V.; Benson, Peter A.; Duncan, Garth; Johnston, Jill C.; Lane, Thomas A.; Matis, George; Olson, John W.; Banning, Davey L.; Greer, Daniel A.; Seidel, Cary M.; Thien, Michael G.

    2012-07-01

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is under construction for the U.S. Department of Energy by Bechtel National, Inc. and subcontractor URS Corporation (contract no. DE-AC27-01RV14136). The plant when completed will be the world's largest nuclear waste treatment facility. Bechtel and URS are tasked with designing, constructing, commissioning, and transitioning the plant to the long term operating contractor to process the legacy wastes that are stored in underground tanks (from nuclear weapons production between the 1940's and the 1980's). Approximately 56 million gallons of radioactive waste is currently stored in these tanks at the Hanford Site in southeastern Washington. There are three major WTP facilities being constructed for processing the tank waste feed. The Pretreatment (PT) facility receives feed where it is separated into a low activity waste (LAW) fraction and a high level waste (HLW) fraction. These fractions are transferred to the appropriate (HLW or LAW) facility, combined with glass former material, and sent to high temperature melters for formation of the glass product. In addition to PT, HLW and LAW, other facilities in WTP include the Laboratory (LAB) for analytical services and the Balance of Facilities (BOF) for plant maintenance, support and utility services. The transfer of staged feed from the waste storage tanks and acceptance in WTP receipt vessels require data for waste acceptance criteria (WAC) parameters from analysis of feed samples. The Data Quality Objectives (DQO) development was a joint team effort between WTP and Tank Operations Contractor (TOC) representatives. The focus of this DQO effort was to review WAC parameters and develop data quality requirements, the results of which will determine whether or not the staged feed can be transferred from the TOC to WTP receipt vessels. The approach involved systematic planning for data collection consistent with EPA guidance for the seven-step DQO process

  11. Photovoltaic module certification/laboratory accreditation criteria development

    SciTech Connect (OSTI)

    Osterwald, C.R. [National Renewable Energy Lab., Golden, CO (United States); Hammond, R.L.; Wood, B.D.; Backus, C.E.; Sears, R.L. [Arizona State Univ., Tempe, AZ (United States); Zerlaut, G.A. [SC-International Inc., Phoenix, AZ (United States); D`Aiello, R.V. [RD Associates, Tempe, AZ (United States)

    1995-04-01

    This document provides an overview of the structure and function of typical product certification/laboratory accreditation programs. The overview is followed by a model program which could serve as the basis for a photovoltaic (PV) module certification/laboratory accreditation program. The model covers quality assurance procedures for the testing laboratory and manufacturer, third-party certification and labeling, and testing requirements (performance and reliability). A 30-member Criteria Development Committee was established to guide, review, and reach a majority consensus regarding criteria for a PV certification/laboratory accreditation program. Committee members represented PV manufacturers, end users, standards and codes organizations, and testing laboratories.

  12. How to Apply the National Register Criteria for Evaluation

    Broader source: Energy.gov [DOE]

    The National Register of Historic Places is the official list of properties recognized to have national, state, or local significance in American history, architecture, archaeology, engineering, and culture. To guide the selection of properties included in the National Register, the National Park Service (NPS) has developed the National Register Criteria for Evaluation. This bulletin explains how the NPS applies these criteria in evaluating the wide range of properties that may be significant in local, state, and national history. It should be used by anyone who must decide if a particular property qualifies for the National Register.

  13. NEVADA TEST SITE WASTE ACCEPTANCE CRITERIA, JUNE 2006

    SciTech Connect (OSTI)

    U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION NEVADA SITE OFFICE

    2006-06-01

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive (LLW) and mixed waste (MW) for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex (RWMC) for storage or disposal.

  14. Constraining the mSUGRA parameter space through entropy and abundance criteria

    SciTech Connect (OSTI)

    Cabral-Rosetti, Luis G.; Mondragon, Myriam; Nunez, Dario; Sussman, Roberto A.; Zavala, Jesus; Nellen, Lukas

    2007-06-19

    We explore the use of two criteria to constrain the allowed parameter space in mSUGRA models; both criteria are based in the calculation of the present density of neutralinos {chi}0 as Dark Matter in the Universe. The first one is the usual ''abundance'' criterion that requieres that present neutralino relic density complies with 0.0945 < {omega}CDMh2 < 0.1287, which are the 2{sigma} bounds according to WMAP. To calculate the relic density we use the public numerical code micrOMEGAS. The second criterion is the original idea presented in [3] that basically applies the microcanonical definition of entropy to a weakly interacting and self-gravitating gas, and then evaluate the change in entropy per particle of this gas between the freeze-out era and present day virialized structures. An 'entropy consistency' criterion emerges by comparing theoretical and empirical estimates of this entropy. One of the objetives of the work is to analyze the joint application of both criteria, already done in [3], to see if their results, using approximations for the calculations of the relic density, agree with the results coming from the exact numerical results of micrOMEGAS. The main objetive of the work is to use this method to constrain the parameter space in mSUGRA models that are inputs for the calculations of micrOMEGAS, and thus to get some bounds on the predictions for the SUSY spectra.

  15. Development of criteria used to establish a background environmental monitoring station

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Fritz, Brad G.; Barnett, J. Matthew; Snyder, Sandra F.; Bisping, Lynn E.; Rishel, Jeremy P.

    2015-03-02

    It is generally considered necessary to measure concentrations of contaminants-of-concern at a background location when conducting atmospheric environmental surveillance. This is because it is recognized that measurements of background concentrations can enhance interpretation of environmental monitoring data. Despite the recognized need for background measurements, there is little published guidance available that describes how to identify an appropriate atmospheric background monitoring location. This paper develops generic criteria that can guide the decision making process for identifying suitable locations for background atmospheric monitoring station. Detailed methods for evaluating some of these criteria are also provided and a case study for establishment ofmore » an atmospheric background surveillance station as part of an environmental surveillance program is described. While the case study focuses on monitoring for radionuclides, the approach is equally valid for any airborne constituent being monitored. The case study shows that implementation of the developed criteria can result in a good, defensible choice for a background atmospheric monitoring location.« less

  16. Design Criteria for Bagless Transfer System (BTS) Packaging System

    SciTech Connect (OSTI)

    RISENMAY, H.R.

    2000-04-26

    This document provides the criteria for the design and installation of a Bagless Transfer System (BTS); Blend, Sieve and Balance Equipment; and Supercritical Fluid Extraction System (SFE). The project consists of 3 major modules: (1) Bagless Transfer System (BTS) Module; (2) Blend, Sieve and Balance Equipment; and (3) Supercritical Fluid Extraction (SFE) Module.

  17. Durability-based design criteria for an automotive structural composite

    SciTech Connect (OSTI)

    Corum, J.M.; Battiste, R.L.; Brinkman, C.R.; Ren, W.; Ruggles, M.B.; Yahr, G.T.

    1998-11-01

    Before composite structures can be widely used in automotive applications, their long-term durability must be assured. The Durability of Lightweight Composite Structures Project at Oak Ridge National Laboratory was established by the US Department of Energy to help provide that assurance. The project is closely coordinated with the Automotive Composites Consortium. The experimentally-based, durability-driven design criteria described in this paper are the result of the initial project thrust. The criteria address a single reference composite, which is an SRIM (Structural Reaction Injection Molded) polyurethane, reinforced with continuous strand, swirl-mat E-glass fibers. The durability issues addressed include the effects of cyclic and sustained loadings, temperature, automotive fluid environments, and low-energy impacts (e.g., tool drops and roadway kickups) on strength, stiffness, and deformation. The criteria provide design analysis guidance, a multiaxial strength criterion, time-independent and time-dependent allowable stresses, rules for cyclic loading, and damage tolerance design guidance. Environmental degradation factors and the degrading effects of prior loadings are included. Efforts are currently underway to validate the criteria by application to a second random-glass-fiber composite. Carbon-fiber composites are also being addressed.

  18. Licensed reactor nuclear safety criteria applicable to DOE reactors

    SciTech Connect (OSTI)

    Not Available

    1991-04-01

    The Department of Energy (DOE) Order DOE 5480.6, Safety of Department of Energy-Owned Nuclear Reactors, establishes reactor safety requirements to assure that reactors are sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that adequately protects health and safety and is in accordance with uniform standards, guides, and codes which are consistent with those applied to comparable licensed reactors. This document identifies nuclear safety criteria applied to NRC (Nuclear Regulatory Commission) licensed reactors. The titles of the chapters and sections of USNRC Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, Rev. 3, are used as the format for compiling the NRC criteria applied to the various areas of nuclear safety addressed in a safety analysis report for a nuclear reactor. In each section the criteria are compiled in four groups: (1) Code of Federal Regulations, (2) US NRC Regulatory Guides, SRP Branch Technical Positions and Appendices, (3) Codes and Standards, and (4) Supplemental Information. The degree of application of these criteria to a DOE-owned reactor, consistent with their application to comparable licensed reactors, must be determined by the DOE and DOE contractor.

  19. Criteria & Review Approach Documents, National Nuclear Security Administration

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2A "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of a table of National Nuclear Security Administration Criteria Review and Approach Documents (CRADS) with links to the CRADs. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs.

  20. Criteria Review and Approach Documents, National Nuclear Security Administration

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2A "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of National Nuclear Security Administration Criteria Review and Approach Documents (CRADS). CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs.

  1. Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant |

    Office of Environmental Management (EM)

    Department of Energy The documents included in this listing are additional references not included in the Phase 2 Radiological Release at the Waste Isolation Pilot Plant, Attachment F: Bibliography and References report. The documents were examined and used to develop the final report. Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant, DOE

  2. Waste acceptance criteria for the Waste Isolation Pilot Plant

    SciTech Connect (OSTI)

    NONE

    1996-04-01

    The Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC), DOE/WIPP-069, was initially developed by a U.S. Department of Energy (DOE) Steering Committee to provide performance requirements to ensure public health and safety as well as the safe handling of transuranic (TRU) waste at the WIPP. This revision updates the criteria and requirements of previous revisions and deletes those which were applicable only to the test phase. The criteria and requirements in this document must be met by participating DOE TRU Waste Generator/Storage Sites (Sites) prior to shipping contact-handled (CH) and remote-handled (RH) TRU waste forms to the WIPP. The WIPP Project will comply with applicable federal and state regulations and requirements, including those in Titles 10, 40, and 49 of the Code of Federal Regulations (CFR). The WAC, DOE/WIPP-069, serves as the primary directive for assuring the safe handling, transportation, and disposal of TRU wastes in the WIPP and for the certification of these wastes. The WAC identifies strict requirements that must be met by participating Sites before these TRU wastes may be shipped for disposal in the WIPP facility. These criteria and requirements will be reviewed and revised as appropriate, based on new technical or regulatory requirements. The WAC is a controlled document. Revised/changed pages will be supplied to all holders of controlled copies.

  3. Earthquake design criteria for small hydro projects in the Philippines

    SciTech Connect (OSTI)

    Martin, P.P.; McCandless, D.H.; Asce, M.

    1995-12-31

    The definition of the seismic environment and seismic design criteria of more than twenty small hydro projects in the northern part of the island of Luzon in the Philippines took a special urgency on the wake of the Magnitude 7.7 earthquake that shook the island on July 17, 1990. The paper describes the approach followed to determine design shaking level criteria at each hydro site consistent with the seismic environment estimated at that same site. The approach consisted of three steps: (1) Seismicity: understanding the mechanisms and tectonic features susceptible to generate seismicity and estimating the associated seismicity levels, (2) Seismic Hazard: in the absence of an accurate historical record, using statistics to determine the expected level of ground shaking at a site during the operational 100-year design life of each Project, and (3) Criteria Selection: finally and most importantly, exercising judgment in estimating the final proposed level of shaking at each site. The resulting characteristics of estimated seismicity and seismic hazard and the proposed final earthquake design criteria are provided.

  4. STRUCTURAL DESIGN CRITERIA FOR TARGET/BLANKET SYSTEM COMPONENT MATERIALS FOR THE ACCELERATOR PRODUCTION OF TRITIUM PROJECT

    SciTech Connect (OSTI)

    W. JOHNSON; R. RYDER; P. RITTENHOUSE

    2001-01-01

    The design of target/blanket system components for the Accelerator Production of Tritium (APT) plant is dependent on the development of materials properties data specified by the designer. These data are needed to verify that component designs are adequate. The adequacy of the data will be related to safety, performance, and economic considerations, and to other requirements that may be deemed necessary by customers and regulatory bodies. The data required may already be in existence, as in the open technical literature, or may need to be generated, as is often the case for the design of new systems operating under relatively unique conditions. The designers' starting point for design data needs is generally some form of design criteria used in conjunction with a specified set of loading conditions and associated performance requirements. Most criteria are aimed at verifying the structural adequacy of the component, and often take the form of national or international standards such as the ASME Boiler and Pressure Vessel Code (ASME B and PV Code) or the French Nuclear Structural Requirements (RCC-MR). Whether or not there are specific design data needs associated with the use of these design criteria will largely depend on the uniqueness of the conditions of operation of the component. A component designed in accordance with the ASME B and PV Code, where no unusual environmental conditions exist, will utilize well-documented, statistically-evaluated developed in conjunction with the Code, and will not be likely to have any design data needs. On the other hand, a component to be designed to operate under unique APT conditions, is likely to have significant design data needs. Such a component is also likely to require special design criteria for verification of its structural adequacy, specifically accounting for changes in materials properties which may occur during exposure in the service environment. In such a situation it is common for the design criteria and

  5. System, apparatus and methods to implement high-speed network analyzers

    DOE Patents [OSTI]

    Ezick, James; Lethin, Richard; Ros-Giralt, Jordi; Szilagyi, Peter; Wohlford, David E

    2015-11-10

    Systems, apparatus and methods for the implementation of high-speed network analyzers are provided. A set of high-level specifications is used to define the behavior of the network analyzer emitted by a compiler. An optimized inline workflow to process regular expressions is presented without sacrificing the semantic capabilities of the processing engine. An optimized packet dispatcher implements a subset of the functions implemented by the network analyzer, providing a fast and slow path workflow used to accelerate specific processing units. Such dispatcher facility can also be used as a cache of policies, wherein if a policy is found, then packet manipulations associated with the policy can be quickly performed. An optimized method of generating DFA specifications for network signatures is also presented. The method accepts several optimization criteria, such as min-max allocations or optimal allocations based on the probability of occurrence of each signature input bit.

  6. Improved technical specifications

    SciTech Connect (OSTI)

    Hoffman, D.R.

    1994-12-31

    Improved technical specifications for nuclear power plants are outlined. The objectives of this work are to improve safety, provide a clearer understanding of safety significance, and ease NRC and industry administrative burdens. Line item improvements, bases, and implementation of the specifications are discussed.

  7. Mode specific dynamics of the H{sub 2} + CH{sub 3} → H + CH{sub 4} reaction studied using quasi-classical trajectory and eight-dimensional quantum dynamics methods

    SciTech Connect (OSTI)

    Wang, Yan; Li, Jun; Guo, Hua E-mail: hguo@unm.edu; Chen, Liuyang; Yang, Minghui E-mail: hguo@unm.edu; Lu, Yunpeng

    2015-10-21

    An eight-dimensional quantum dynamical model is proposed and applied to the title reaction. The reaction probabilities and integral cross sections have been determined for both the ground and excited vibrational states of the two reactants. The results indicate that the H{sub 2} stretching and CH{sub 3} umbrella modes, along with the translational energy, strongly promote the reactivity, while the CH{sub 3} symmetric stretching mode has a negligible effect. The observed mode specificity is confirmed by full-dimensional quasi-classical trajectory calculations. The mode specificity can be interpreted by the recently proposed sudden vector projection model, which attributes the enhancement effects of the reactant modes to their strong couplings with the reaction coordinate at the transition state.

  8. Functional design criteria 241-AP-102 Flexible Receiver System

    SciTech Connect (OSTI)

    Roblyer, S.P.

    1995-02-16

    A mixer pump was installed in the 1.07 m (42-in.) riser of the central pump pit of tank 241-AP-102 to mitigate potential fluid separation particle sedimentation by mixing the tank`s contents. The mixer pump performed this function until failure. Its removal is now necessary to meet possible tank content removal commitments or other corrective actions. The proposed removal procedure requires a flexible receiver that will provide a barrier to contamination during removal and transfer of the pump to the mixer pump storage container. This document describes the functional design criteria of the flexible receiver. These criteria include the functional and performance requirements of the flexible receiver as a barrier to contamination during normal conditions and contingencies and the instrumentation requirements.

  9. Self-Consistent Criteria for Evaluation of Neutron Interaction

    SciTech Connect (OSTI)

    Henry H.F,Newlon C.E.,Knight J.R.

    2007-08-02

    New safe interaction criteria for containers of fissionable materials handled at the Oak Ridge Gaseous Diffusion Plant have been developed on the basis of an interaction theory using the basic concepts of a safe solid angle subtended by interacting containers, and the multiplication factor as determined by two-group theory for an individually safe containers The calculated results agree satisfactorily with experimental data obtained with identical interacting units involving both cylinders and slabs containing highly enriched uranium, the core compositions of which were varied between H/U-235 atomic ratios of 44.3 and 337. The application of the derived interaction criteria to items containing material with low moderation or low U-235 assay, and to containers for which nuclear safety is dependent upon control of the U-235 mass or U-235 concentration is discussed.

  10. MCO combustible gas management leak test acceptance criteria

    SciTech Connect (OSTI)

    SHERRELL, D.L.

    1999-05-11

    Existing leak test acceptance criteria for mechanically sealed and weld sealed multi-canister overpacks (MCO) were evaluated to ensure that MCOs can be handled and stored in stagnant air without compromising the Spent Nuclear Fuel Project's overall strategy to prevent accumulation of combustible gas mixtures within MCO's or within their surroundings. The document concludes that the integrated leak test acceptance criteria for mechanically sealed and weld sealed MCOs (1 x 10{sup -5} std cc/sec and 1 x 10{sup -7} std cc/sec, respectively) are adequate to meet all current and foreseeable needs of the project, including capability to demonstrate compliance with the NFPA 60 Paragraph 3-3 requirement to maintain hydrogen concentrations [within the air atmosphere CSB tubes] t or below 1 vol% (i.e., at or below 25% of the LFL).