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1

Source and replica calculations  

Science Conference Proceedings (OSTI)

The starting point of the Hiroshima-Nagasaki Dose Reevaluation Program is the energy and directional distributions of the prompt neutron and gamma-ray radiation emitted from the exploding bombs. A brief introduction to the neutron source calculations is presented. The development of our current understanding of the source problem is outlined. It is recommended that adjoint calculations be used to modify source spectra to resolve the neutron discrepancy problem.

Whalen, P.P.

1994-02-01T23:59:59.000Z

2

GROA AIRBORNE RELEASE DISPERSION FACTOR CALCULATION  

Science Conference Proceedings (OSTI)

The purpose of this document is to calculate airborne release dispersion factors ({chi}/Q) for the surface and subsurface facilities at the Geological Repository Operations Area (GROA). The calculated {chi}/Q values may be used to estimate radiological consequences to workers for potential releases from normal operations and event sequences for License Application. The scope of this document is to provide estimates of {chi}/Q values at potential onsite receptors from facility releases, under normal operating conditions and event sequences.

J. Wang

2005-03-21T23:59:59.000Z

3

Thermal Conversion Factor Source Documentation  

U.S. Energy Information Administration (EIA)

national annual quantity-weighted average conversion factors for conventional, reformulated, and oxygenated motor gasolines (see Table A3). The factor ...

4

Calculating CO2 Emissions from Mobile Sources | Open Energy Information  

Open Energy Info (EERE)

Calculating CO2 Emissions from Mobile Sources Calculating CO2 Emissions from Mobile Sources Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Calculating CO2 Emissions from Mobile Sources,GHG Protocol Agency/Company /Organization: Aether, Environmental Data Services, Aether, Environmental Data Services Sector: Energy Focus Area: GHG Inventory Development, Industry, Transportation Topics: GHG inventory, Potentials & Scenarios Resource Type: Guide/manual Complexity/Ease of Use: Not Available Website: cf.valleywater.org/Water/Where_Your_Water_Comes_From/Water%20Supply%20 Cost: Free References: http://cf.valleywater.org/Water/Where_Your_Water_Comes_From/Water%20Supply%20and%20Infrastructure%20Planning/Climate%20Change/Guidance_for_mobile_emissions_GHG_protocol.pdf Related Tools Tool and Calculator (Transit, Fuel)

5

A Computer Program for Calculating Tetroon Inflation-Factor Nomographs  

Science Conference Proceedings (OSTI)

A slow but steady increase in the use of tetroons for tracing atmospheric air trajectories has prompted the development of an automatic method for calculating accurate tetroon inflation factors to float tetroons at desired elevations. The ...

Walter H. Hoecker

1981-08-01T23:59:59.000Z

6

Selection of models to calculate the LLW source term  

Science Conference Proceedings (OSTI)

Performance assessment of a LLW disposal facility begins with an estimation of the rate at which radionuclides migrate out of the facility (i.e., the source term). The focus of this work is to develop a methodology for calculating the source term. In general, the source term is influenced by the radionuclide inventory, the wasteforms and containers used to dispose of the inventory, and the physical processes that lead to release from the facility (fluid flow, container degradation, wasteform leaching, and radionuclide transport). In turn, many of these physical processes are influenced by the design of the disposal facility (e.g., infiltration of water). The complexity of the problem and the absence of appropriate data prevent development of an entirely mechanistic representation of radionuclide release from a disposal facility. Typically, a number of assumptions, based on knowledge of the disposal system, are used to simplify the problem. This document provides a brief overview of disposal practices and reviews existing source term models as background for selecting appropriate models for estimating the source term. The selection rationale and the mathematical details of the models are presented. Finally, guidance is presented for combining the inventory data with appropriate mechanisms describing release from the disposal facility. 44 refs., 6 figs., 1 tab.

Sullivan, T.M. (Brookhaven National Lab., Upton, NY (United States))

1991-10-01T23:59:59.000Z

7

Calculation of dose to soft tisse from implanted beta sources  

E-Print Network (OSTI)

Treatment of Arterio-Venous Malformation (AVM) requires the occlusion of the unwanted arteries. Irradiation of a blood vessel wall with beta particles causes it to be permanently blocked by multiplication of the endothelial cells. For this purpose, spherical radioactive particles are injected into these arteries. This study deals with the development of BRAIN-DOSES, a computer code based on VARSKIN MOD2 and SADDE MOD2, which evaluates gamma and beta dose distributions for radioactive sources with five different geometries: point, line, shell cylinder, solid cylinder and solid sphere. Since the particles injected into the blood vessels can be modeled as a line of spheres, this work focuses on the development of a computational method for estimating the spatial distribution of absorbed dose around a line of spheres. BRAIN-DOSES uses integration of Berger point kernels over the source volume, employing the scaled point kernels tabulated by Berger in 1971. This method requires calculation of the beta particle path within the two media crossed, tissue and source material. Consequently, besides the computational approach, this study describes a detailed geometrical approach of the problem. Results obtained from calculations with BRAIN-DOSES have been used to evaluate the beta dose distribution in the capillary walls of the rete of pigs, a vascular system which may model an AVM. The source was a 418 CI line of spheres made of a mixture of 42.8% hydrated polyacrylonitrile (PAN), 49.8% powdered Pt-197 and 7.4% powdered Pr-142 (in weight percentage). The sphere diameters were from 150 to 350 gm.

Dauffy, Lucile

1998-01-01T23:59:59.000Z

8

Acceleration of Monte Carlo Criticality Calculations Using Deterministic-Based Starting Sources  

SciTech Connect

A new automatic approach that uses approximate deterministic solutions for providing the starting fission source for Monte Carlo eigenvalue calculations was evaluated in this analysis. By accelerating the Monte Carlo source convergence and decreasing the number of cycles that has to be skipped before the tallies estimation, this approach was found to increase the efficiency of the overall simulation, even with the inclusion of the extra computational time required by the deterministic calculation. This approach was also found to increase the reliability of the Monte Carlo criticality calculations of loosely coupled systems because the use of the better starting source reduces the likelihood of producing an undersampled k{sub eff} due to the inadequate source convergence. The efficiency improvement was demonstrated using two of the standard test problems devised by the OECD/NEA Expert Group on Source Convergence in Criticality-Safety Analysis to measure the source convergence in Monte Carlo criticality calculations. For a fixed uncertainty objective, this approach increased the efficiency of the overall simulation by factors between 1.2 and 3 depending on the difficulty of the source convergence in these problems. The reliability improvement was demonstrated in a modified version of the 'k{sub eff} of the world' problem that was specifically designed to demonstrate the limitations of the current Monte Carlo power iteration techniques. For this problem, the probability of obtaining a clearly undersampled k{sub eff} decreased from 5% with a uniform starting source to zero with a deterministic starting source when batch sizes with more than 15,000 neutron/cycle were used.

Ibrahim, A. [University of Wisconsin; Peplow, Douglas E. [ORNL; Wagner, John C [ORNL; Mosher, Scott W [ORNL; Evans, Thomas M [ORNL

2012-01-01T23:59:59.000Z

9

MEASURED AND CALCULATED HEATING AND DOSE RATES FOR THE HFIR HB4 BEAM TUBE AND COLD SOURCE  

SciTech Connect

The High Flux Isotope Reactor at the Oak Ridge National Laboratory was upgraded to install a cold source in horizontal beam tube number 4. Calculations were performed and measurements were made to determine heating within the cold source and dose rates within and outside a shield tunnel surrounding the beam tube. This report briefly describes the calculations and presents comparisons of the measured and calculated results. Some calculated dose rates are in fair to good agreement with the measured results while others, particularly those at the shield interfaces, differ greatly from the measured results. Calculated neutron exposure to the Teflon seals in the hydrogen transfer line is about one fourth of the measured value, underpredicting the lifetime by a factor of four. The calculated cold source heating is in good agreement with the measured heating.

Slater, Charles O [ORNL; Primm, Trent [ORNL; Pinkston, Daniel [ORNL; Cook, David Howard [ORNL; Selby, Douglas L [ORNL; Ferguson, Phillip D [ORNL; Bucholz, James A [ORNL; Popov, Emilian L [ORNL

2009-03-01T23:59:59.000Z

10

Back-calculating emission rates for ammonia and particulate matter from area sources using dispersion modeling  

E-Print Network (OSTI)

Engineering directly impacts current and future regulatory policy decisions. The foundation of air pollution control and air pollution dispersion modeling lies in the math, chemistry, and physics of the environment. Therefore, regulatory decision making must rely upon sound science and engineering as the core of appropriate policy making (objective analysis in lieu of subjective opinion). This research evaluated particulate matter and ammonia concentration data as well as two modeling methods, a backward Lagrangian stochastic model and a Gaussian plume dispersion model. This analysis assessed the uncertainty surrounding each sampling procedure in order to gain a better understanding of the uncertainty in the final emission rate calculation (a basis for federal regulation), and it assessed the differences between emission rates generated using two different dispersion models. First, this research evaluated the uncertainty encompassing the gravimetric sampling of particulate matter and the passive ammonia sampling technique at an animal feeding operation. Future research will be to further determine the wind velocity profile as well as determining the vertical temperature gradient during the modeling time period. This information will help quantify the uncertainty of the meteorological model inputs into the dispersion model, which will aid in understanding the propagated uncertainty in the dispersion modeling outputs. Next, an evaluation of the emission rates generated by both the Industrial Source Complex (Gaussian) model and the WindTrax (backward-Lagrangian stochastic) model revealed that the calculated emission concentrations from each model using the average emission rate generated by the model are extremely close in value. However, the average emission rates calculated by the models vary by a factor of 10. This is extremely troubling. In conclusion, current and future sources are regulated based on emission rate data from previous time periods. Emission factors are published for regulation of various sources, and these emission factors are derived based upon back-calculated model emission rates and site management practices. Thus, this factor of 10 ratio in the emission rates could prove troubling in terms of regulation if the model that the emission rate is back-calculated from is not used as the model to predict a future downwind pollutant concentration.

Price, Jacqueline Elaine

2004-08-01T23:59:59.000Z

11

Analysis Of Factors Affecting Natural Source Slf Electromagnetic  

Open Energy Info (EERE)

Factors Affecting Natural Source Slf Electromagnetic Factors Affecting Natural Source Slf Electromagnetic Exploration At Geothermal Wells Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Journal Article: Analysis Of Factors Affecting Natural Source Slf Electromagnetic Exploration At Geothermal Wells Details Activities (0) Areas (0) Regions (0) Abstract: The Super Low Frequency (SLF) electromagnetic exploration was performed by using a nature source SLF electromagnetic detector at two geothermal wells in Peking University. The data of the SLF electromagnetic exploration at well JR-119 and JR-168 were obtained with the observation of continued five days and four times per day at well JR-119 and of one day at well JR-168. Based on these data, the influencing factors of the SI-F electromagnetic exploration were analyzed, which included the relationship

12

Calculating Chiller Emissions and Source Energy Use: Commercial Cooling Update: Issue 12, November 1995  

Science Conference Proceedings (OSTI)

Refrigerant phaseouts are raising questions about the environmental impacts of different types of chillers. This Update introduces a hand-calculation method for estimating the emissions and source energy use (i.e., fossil fuel use) of gas and electric chillers. The update also reviews the two methods of chiller systems emissions production: refrigerant losses and fossil fuel combustion; discusses meeting NOx regulations; use of source energy; and examines existing calculation approaches as opposed to a s...

1995-12-07T23:59:59.000Z

13

Neutron source in the MCNPX shielding calculating for electron accelerator driven facility  

SciTech Connect

Argonne National Laboratory (ANL) of USA and Kharkov Inst. of Physics and Technology (KIPT) of Ukraine have been collaborating on the design development of an experimental neutron source facility. It is an accelerator driven system (ADS) utilizing a subcritical assembly driven by electron accelerator. The facility will be utilized for performing basic and applied nuclear researches, producing medical isotopes, and training young nuclear specialists. Monte Carlo code MCNPX has been utilized as a design tool due to its capability to transport electrons, photons, and neutrons at high energies. However the facility shielding calculations with MCNPX need enormous computational resources and the small neutron yield per electron makes sampling difficulty for the Monte Carlo calculations. A method, based on generating and utilizing neutron source file, was proposed and tested. This method reduces significantly the required computer resources and improves the statistics of the calculated neutron dose outside the shield boundary. However the statistical errors introduced by generating the neutron source were not directly represented in the results, questioning the validity of this methodology, because an insufficiently sampled neutron source can cause error on the calculated neutron dose. This paper presents a procedure for the validation of the generated neutron source file. The impact of neutron source statistic on the neutron dose is examined by calculating the neutron dose as a function of the number of electron particles used for generating the neutron source files. When the value of the calculated neutron dose converges, it means the neutron source has scored sufficient records and statistic does not have apparent impact on the calculated neutron dose. In this way, the validity of neutron source and the shield analyses could be verified. (authors)

Zhong, Z.; Gohar, Y. [Nuclear Engineering Div., Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439 (United States)

2012-07-01T23:59:59.000Z

14

Real-Time Sky-View Factor Calculation and Approximation  

Science Conference Proceedings (OSTI)

Previously, the acquisition of sky-view factor data for climate studies has been time consuming and dependent on postprocessing. However, advances in technology now mean that techniques using fish-eye imagery can be algorithmically processed in ...

L. Chapman; J. E. Thornes

2004-05-01T23:59:59.000Z

15

Calculation of extremity neutron fluence-to-dose equivalent conversion factors  

E-Print Network (OSTI)

Neutron fluence-to-dose equivalent conversion factors are calculated for three types of finger and wrist extremity phantoms: (1) the polymethyl methacrylate models specified by the U.S. Department of Energy Laboratory Accreditation Program for Personnel Dosimetry Systems (DOELAP); (2) the tissue-and-bone phantoms suggested by Pacific Northwest National Laboratory; and (3) the Radiology Support Devices (RSD) Inc. RS-122T an-n/shoulder phantom. Extremity factors are determined at shallow surface and bone levels for bare, D20moderated and polyethylene moderated 112Cf. The DOELAP free-field calibration geometry and a realistic glovebox scenario are simulated using a Monte Carlo neutron and photon transport code. Calculated DOELAP and RSD extremity fluence-to-dose equivalent conversion factors for the free-field calibration geometry are 1 to 9 percent lower than the calculated whole-body conversion factor. The tissue-and-bone phantoms exhibit conversion factors 1 to 10 percent greater than the whole-body factor. Glovebox fluence-to-dose equivalent conversion factors range from 12 percent less than to 128 percent greater than calculated free-field whole-body conversion factors. A preliminary evaluation of the application of the calculated fluence-to-dose equivalent conversion factors to Los Alamos National Laboratory extremity dosimeter correction factors is performed.

Wood-Zika, Annmarie Ruth

1997-01-01T23:59:59.000Z

16

THE CALCULATION OF BURNABLE POISON CORRECTION FACTORS FOR PWR FRESH FUEL ACTIVE COLLAR MEASUREMENTS  

SciTech Connect

Verification of commercial low enriched uranium light water reactor fuel takes place at the fuel fabrication facility as part of the overall international nuclear safeguards solution to the civilian use of nuclear technology. The fissile mass per unit length is determined nondestructively by active neutron coincidence counting using a neutron collar. A collar comprises four slabs of high density polyethylene that surround the assembly. Three of the slabs contain {sup 3}He filled proportional counters to detect time correlated fission neutrons induced by an AmLi source placed in the fourth slab. Historically, the response of a particular collar design to a particular fuel assembly type has been established by careful cross-calibration to experimental absolute calibrations. Traceability exists to sources and materials held at Los Alamos National Laboratory for over 35 years. This simple yet powerful approach has ensured consistency of application. Since the 1980's there has been a steady improvement in fuel performance. The trend has been to higher burn up. This requires the use of both higher initial enrichment and greater concentrations of burnable poisons. The original analytical relationships to correct for varying fuel composition are consequently being challenged because the experimental basis for them made use of fuels of lower enrichment and lower poison content than is in use today and is envisioned for use in the near term. Thus a reassessment of the correction factors is needed. Experimental reassessment is expensive and time consuming given the great variation between fuel assemblies in circulation. Fortunately current modeling methods enable relative response functions to be calculated with high accuracy. Hence modeling provides a more convenient and cost effective means to derive correction factors which are fit for purpose with confidence. In this work we use the Monte Carlo code MCNPX with neutron coincidence tallies to calculate the influence of Gd{sub 2}O{sub 3} burnable poison on the measurement of fresh pressurized water reactor fuel. To empirically determine the response function over the range of historical and future use we have considered enrichments up to 5 wt% {sup 235}U/{sup tot}U and Gd weight fractions of up to 10 % Gd/UO{sub 2}. Parameterized correction factors are presented.

Croft, Stephen [Los Alamos National Laboratory; Favalli, Andrea [Los Alamos National Laboratory; Swinhoe, Martyn T. [Los Alamos National Laboratory

2012-06-19T23:59:59.000Z

17

Source Energy and Emission Factors for Energy Use in Buildings (Revised)  

SciTech Connect

This document supports the other measurement procedures and all building energy-monitoring projects by providing methods to calculate the source energy and emissions from the energy measured at the building. Energy and emission factors typically account for the conversion inefficiencies at the power plant and the transmission and distribution losses from the power plant to the building. The energy and emission factors provided here also include the precombustion effects, which are the energy and emissions associated with extracting, processing, and delivering the primary fuels to the point of conversion in the electrical power plants or directly in the buildings.

Deru, M.; Torcellini, P.

2007-06-01T23:59:59.000Z

18

A diffusion theory model for optimization calculations of cold neutron sources  

DOE Green Energy (OSTI)

This summary describes a simple two-group diffusion model of an infinite slab, liquid deuterium (LD/sub 2/) cold source. The simplicity of the model permits us to obtain an analytical solution from which we can deduce the reason for the optimum thickness based solely on diffusion type phenomena. Also, a second more sophisticated model is described, and the results compared to a deterministic transport calculation. The good (particularly qualitative) agreement between the results suggests that diffusion theory methods can be used in parametric and optimization studies in order to avoid the generally more expensive transport calculations. 5 refs., 1 fig.

Azmy, Y.Y.

1987-01-01T23:59:59.000Z

19

Implementation and qualification of neutronic calculation methodology in subcritical reactors driven by external neutron sources and applications.  

E-Print Network (OSTI)

??This works had as goal to investigate calculational methodologies on subcritical source driven reactor, such as Accelerator Driven Subcritical Reactor (ADSR) and Fusion Driven Subcritical (more)

Thiago Carluccio

2011-01-01T23:59:59.000Z

20

The unit cost factors and calculation methods for decommissioning - Cost estimation of nuclear research facilities  

SciTech Connect

Available in abstract form only. Full text of publication follows: The uncertainties of decommissioning costs increase high due to several conditions. Decommissioning cost estimation depends on the complexity of nuclear installations, its site-specific physical and radiological inventories. Therefore, the decommissioning costs of nuclear research facilities must be estimated in accordance with the detailed sub-tasks and resources by the tasks of decommissioning activities. By selecting the classified activities and resources, costs are calculated by the items and then the total costs of all decommissioning activities are reshuffled to match with its usage and objectives. And the decommissioning cost of nuclear research facilities is calculated by applying a unit cost factor method on which classification of decommissioning works fitted with the features and specifications of decommissioning objects and establishment of composition factors are based. Decommissioning costs of nuclear research facilities are composed of labor cost, equipment and materials cost. Of these three categorical costs, the calculation of labor costs are very important because decommissioning activities mainly depend on labor force. Labor costs in decommissioning activities are calculated on the basis of working time consumed in decommissioning objects and works. The working times are figured out of unit cost factors and work difficulty factors. Finally, labor costs are figured out by using these factors as parameters of calculation. The accuracy of decommissioning cost estimation results is much higher compared to the real decommissioning works. (authors)

Kwan-Seong Jeong; Dong-Gyu Lee; Chong-Hun Jung; Kune-Woo Lee [Korea Atomic Energy Research Institute, Deokjin-dong 150, Yuseong-gu, Daejeon 305-353 (Korea, Republic of)

2007-07-01T23:59:59.000Z

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


21

The Linac Coherent Light Source at SLAC. Radiological Considerations and Shielding calculations  

Science Conference Proceedings (OSTI)

The Linac Coherent Light Source (LCLS) at SLAC will be the world's first X-ray free electron laser when it becomes operational in 2009. Pulses of X-ray laser light from LCLS will be many orders of magnitude brighter and several orders of magnitude shorter than what can be produced by other X-ray sources available in the world. These characteristics will enable frontier new science in many areas. This paper describes the LCLS beam parameters and its lay-out. Results of the Monte Carlo calculations for the shielding design of the electron dump line, radiation damage to undulator, the residual radiation and the soil activation around the electron dump are presented.

Mao, X.S.; Fasso, A.; Nakao, N.; Rokni, S.H.; Vincke, H.; /SLAC

2005-12-02T23:59:59.000Z

22

Computational Benchmark Calculations Relevant to the Neutronic Design of the Spallation Neutron Source (SNS)  

Science Conference Proceedings (OSTI)

The Spallation Neutron Source (SNS) will provide an intense source of low-energy neutrons for experimental use. The low-energy neutrons are produced by the interaction of a high-energy (1.0 GeV) proton beam on a mercury (Hg) target and slowed down in liquid hydrogen or light water moderators. Computer codes and computational techniques are being benchmarked against relevant experimental data to validate and verify the tools being used to predict the performance of the SNS. The LAHET Code System (LCS), which includes LAHET, HTAPE ad HMCNP (a modified version of MCNP version 3b), have been applied to the analysis of experiments that were conducted in the Alternating Gradient Synchrotron (AGS) facility at Brookhaven National Laboratory (BNL). In the AGS experiments, foils of various materials were placed around a mercury-filled stainless steel cylinder, which was bombarded with protons at 1.6 GeV. Neutrons created in the mercury target, activated the foils. Activities of the relevant isotopes were accurately measured and compared with calculated predictions. Measurements at BNL were provided in part by collaborating scientists from JAERI as part of the AGS Spallation Target Experiment (ASTE) collaboration. To date, calculations have shown good agreement with measurements.

Gallmeier, F.X.; Glasgow, D.C.; Jerde, E.A.; Johnson, J.O.; Yugo, J.J.

1999-11-14T23:59:59.000Z

23

External dose-rate conversion factors for calculation of dose to the public  

SciTech Connect

This report presents a tabulation of dose-rate conversion factors for external exposure to photons and electrons emitted by radionuclides in the environment. This report was prepared in conjunction with criteria for limiting dose equivalents to members of the public from operations of the US Department of Energy (DOE). The dose-rate conversion factors are provided for use by the DOE and its contractors in performing calculations of external dose equivalents to members of the public. The dose-rate conversion factors for external exposure to photons and electrons presented in this report are based on a methodology developed at Oak Ridge National Laboratory. However, some adjustments of the previously documented methodology have been made in obtaining the dose-rate conversion factors in this report. 42 refs., 1 fig., 4 tabs.

Not Available

1988-07-01T23:59:59.000Z

24

Calculation of conversion factors for effective dose for various interventional radiology procedures  

Science Conference Proceedings (OSTI)

Purpose: To provide dose-area-product (DAP) to effective dose (E) conversion factors for complete interventional procedures, based on in-the-field clinical measurements of DAP values and using tabulated E/DAP conversion factors for single projections available from the literature. Methods: Nine types of interventional procedures were performed on 84 patients with two angiographic systems. Different calibration curves (with and without patient table attenuation) were calculated for each DAP meter. Clinical and dosimetric parameters were recorded in-the-field for each projection and for all patients, and a conversion factor linking DAP and effective doses was derived for each complete procedure making use of published, Monte Carlo calculated conversion factors for single static projections. Results: Fluoroscopy time and DAP values for the lowest-dose procedure (biliary drainage) were approximately 3-fold and 13-fold lower, respectively, than those for the highest-dose examination (transjugular intrahepatic portosystemic shunt, TIPS). Median E/DAP conversion factors from 0.12 (abdominal percutaneous transluminal angioplasty) to 0.25 (Nephrostomy) mSvGy{sup -1} cm{sup -2} were obtained and good correlations between E and DAP were found for all procedures, with R{sup 2} coefficients ranging from 0.80 (abdominal angiography) to 0.99 (biliary stent insertion, Nephrostomy and TIPS). The DAP values obtained in this study showed general consistency with the values provided in the literature and median E values ranged from 4.0 mSv (biliary drainage) to 49.6 mSv (TIPS). Conclusions: Values of E/DAP conversion factors were derived for each procedure from a comprehensive analysis of projection and dosimetric data: they could provide a good evaluation for the stochastic effects. These results can be obtained by means of a close cooperation between different interventional professionals involved in patient care and dose optimization.

Compagnone, Gaetano; Giampalma, Emanuela; Domenichelli, Sara; Renzulli, Matteo; Golfieri, Rita [Medical Physics Department, S. Orsola-Malpighi University Hospital, Via Massarenti 9, 40138 Bologna (Italy); Radiology Department, S. Orsola-Malpighi University Hospital, Via Massarenti 9, 40138 Bologna (Italy); Medical Physics Department, S. Orsola-Malpighi University Hospital, Via Massarenti 9, 40138 Bologna (Italy); Radiology Department, S. Orsola-Malpighi University Hospital, Via Massarenti 9, 40138 Bologna (Italy)

2012-05-15T23:59:59.000Z

25

Scoping Analysis of Source Term and Functional Containment Attenuation Factors  

SciTech Connect

In order to meet future regulatory requirements, the Next Generation Nuclear Plant (NGNP) Project must fully establish and validate the mechanistic modular high temperature gas-cooled reactor (HTGR) source term. This is not possible at this stage in the project, as significant uncertainties in the final design remain unresolved. In the interim, however, there is a need to establish an approximate characterization of the source term. The NGNP team developed a simplified parametric model to establish mechanistic source term estimates for a set of proposed HTGR configurations.

Pete Lowry

2012-10-01T23:59:59.000Z

26

Scoping Analysis of Source Term and Functional Containment Attenuation Factors  

SciTech Connect

In order to meet future regulatory requirements, the Next Generation Nuclear Plant (NGNP) Project must fully establish and validate the mechanistic modular high temperature gas-cooled reactor (HTGR) source term. This is not possible at this stage in the project, as significant uncertainties in the final design remain unresolved. In the interim, however, there is a need to establish an approximate characterization of the source term. The NGNP team developed a simplified parametric model to establish mechanistic source term estimates for a set of proposed HTGR configurations.

Pete Lowry

2012-01-01T23:59:59.000Z

27

Scoping Analysis of Source Term and Functional Containment Attenuation Factors  

SciTech Connect

In order to meet future regulatory requirements, the Next Generation Nuclear Plant (NGNP) Project must fully establish and validate the mechanistic modular high temperature gas-cooled reactor (HTGR) source term. This is not possible at this stage in the project, as significant uncertainties in the final design remain unresolved. In the interim, however, there is a need to establish an approximate characterization of the source term. The NGNP team developed a simplified parametric model to establish mechanistic source term estimates for a set of proposed HTGR configurations.

Pete Lowry

2012-02-01T23:59:59.000Z

28

Sources of uncertainty in the calculation of loads on supports of piping systems  

SciTech Connect

Loads on piping systems are obtained from an analysis of the piping system. The piping system analysis involves uncertainties from various sources. These sources of uncertainties are discussed and ranges of uncertainties are illustrated by simple examples. The sources of uncertainties are summarized and assigned a judgmental ranking of the typical relative significance of the uncertainty.

Rodabaugh, E.C.

1984-06-01T23:59:59.000Z

29

ANL/APS/LS-309 Design Calculations for the Advanced Photon Source Safety Shutters P. K. Job, Advanced Photon Source  

E-Print Network (OSTI)

A safety shutter at the Advanced Photon Source (APS) is a remotely actuated device that prevents a photon beam from traveling down a beamline into an experimental enclosure. All APS safety shutters are designed to be redundant. When the shutter is closed, two shielding blocks are positioned to stop bremsstrahlung and the synchrotron

B. J. Micklich; Intense Pulsed; Neutron Source

2005-01-01T23:59:59.000Z

30

Tanning bed use, deviance regulation theory, and source factors  

E-Print Network (OSTI)

Tanning bed use, especially among young, white females, has become a serious health problem in the United States. Those who use tanning beds value a tanned appearance; thus, one possible way to get individuals to stop using tanning beds is to persuade them to begin using an alternative method: a sunless tanner. This study sought to use persuasive messages to encourage individuals to both stop using tanning beds and start using a sunless tanner. Deviance Regulation Theory (DRT) was used to design three messages, and source expertise was manipulated (high and low). In addition, attitudes, perceived norms, benefits and threats about tanning were examined. Results indicate that the combination of DRT message design and source expertise produced several message conditions that were effective at decreasing tanning bed use intent. No combined message condition was effective at changing sunless tanner use intent. DRT message design alone did not produce results, nor did source expertise. Tanning attitudes were influenced by reference groups, and perceived norms about tanning predicted individuals tanning bed use for several reference groups. In addition, there was an interaction between benefits and threats of tanning.

Head, Katharine J.

2008-12-01T23:59:59.000Z

31

Using Factor Analysis to Attribute Health Impacts to Particulate Pollution Sources1  

NLE Websites -- All DOE Office Websites (Extended Search)

Factor Analysis to Attribute Health Impacts to Particulate Factor Analysis to Attribute Health Impacts to Particulate Pollution Sources 1 Thomas Grahame U. S. Department of Energy Washington, DC George Hidy Envair/Aerochem Placitas, NM ABSTRACT Laden et al. (2000) recently reported results of applying factor analysis to data taken in six cities from1979 to1988, identifying airborne particle sources potentially affecting daily mortality. These authors sought relationships between source groups and risk measures using source tracer elements, Se (coal combustion), Pb (light duty motor vehicle sources), and Si (crustal--soil dispersion). Combined data analyses of this kind may overlook the complexity of source contributions, which have common tracer elements. In one of the cities, Boston for example, the authors found coal combustion

32

Monte Carlo calculated TG-60 dosimetry parameters for the {beta}{sup -} emitter {sup 153}Sm brachytherapy source  

SciTech Connect

Purpose: The formalism recommended by Task Group 60 (TG-60) of the American Association of Physicists in Medicine (AAPM) is applicable for {beta} sources. Radioactive biocompatible and biodegradable {sup 153}Sm glass seed without encapsulation is a {beta}{sup -} emitter radionuclide with a short half-life and delivers a high dose rate to the tumor in the millimeter range. This study presents the results of Monte Carlo calculations of the dosimetric parameters for the {sup 153}Sm brachytherapy source. Methods: Version 5 of the (MCNP) Monte Carlo radiation transport code was used to calculate two-dimensional dose distributions around the source. The dosimetric parameters of AAPM TG-60 recommendations including the reference dose rate, the radial dose function, the anisotropy function, and the one-dimensional anisotropy function were obtained. Results: The dose rate value at the reference point was estimated to be 9.21{+-}0.6 cGy h{sup -1} {mu}Ci{sup -1}. Due to the low energy beta emitted from {sup 153}Sm sources, the dose fall-off profile is sharper than the other beta emitter sources. The calculated dosimetric parameters in this study are compared to several beta and photon emitting seeds. Conclusions: The results show the advantage of the {sup 153}Sm source in comparison with the other sources because of the rapid dose fall-off of beta ray and high dose rate at the short distances of the seed. The results would be helpful in the development of the radioactive implants using {sup 153}Sm seeds for the brachytherapy treatment.

Sadeghi, Mahdi; Taghdiri, Fatemeh; Hamed Hosseini, S.; Tenreiro, Claudio [Agricultural, Medical and Industrial School, P.O. Box 31485-498, Karaj (Iran, Islamic Republic of); Engineering Faculty, Research and Science Campus, Islamic Azad University, Tehran (Iran, Islamic Republic of); Department of Energy Science, SungKyunKwan University, 300 Cheoncheon-dong, Suwon (Korea, Republic of)

2010-10-15T23:59:59.000Z

33

Calculated photon KERMA factors based on the LLNL EGDL (Evaluated Gamma-Ray Data Library) data file  

DOE Green Energy (OSTI)

Photon (Gamma-Ray) KERMA factors calculated from the LLNL EGDL (Evaluated Gamma-Ray Data Library) file are tabulated for the elements from Z=1 to Z=30 and for 15 composite materials. The KERMA factors are presented for 191 energy groups over the incident photon energy range from 100 eV to 100 MeV. 3 refs.

Howerton, R.J.

1986-10-10T23:59:59.000Z

34

Software system for calculation and analysis of electrical power, derived from renewable energy sources  

Science Conference Proceedings (OSTI)

The software system for modeling and analysis of the processes of electric power conversion of renewable energy sources (solar radiation and wind velocity) is described. The characteristics of the generators and specific climatic conditions of the geographical ... Keywords: graphical dependences, photovoltaics and wind turbine generators, programme models

Katerina Gabrovska; Nicolay Mihailov

2003-06-01T23:59:59.000Z

35

Dynamical mass generation by source inversion: Calculating the mass gap of the Gross-Neveu model  

E-Print Network (OSTI)

We probe the U(N) Gross-Neveu model with a source-term $J\\bar{\\Psi}\\Psi$. We find an expression for the renormalization scheme and scale invariant source $\\hat{J}$, as a function of the generated mass gap. The expansion of this function is organized in such a way that all scheme and scale dependence is reduced to one single parameter d. We get a non-perturbative mass gap as the solution of $\\hat{J}=0$. In one loop we find that any physical choice for d gives good results for high values of N. In two loops we can determine d self-consistently by the principle of minimal sensitivity and find remarkably accurate results for N>2.

K. Van Acoleyen; H. Verschelde

2001-11-20T23:59:59.000Z

36

Neutronic Design Calculations on Moderators for the Spallation Neutron Source (SNS)  

DOE Green Energy (OSTI)

The Spallation Neutron Source (SNS) to be built at the Oak Ridge National Laboratory will provide an intense source of neutrons for a large variety of experiments. It consists of a high-energy (1-GeV) and high-power ({approximately}1-MW) proton accelerator, an accumulator ring, together with a target station and an experimental area. In the target itself, the proton beam will produce neutrons via the spallation process and these will be converted to low-energy (<2-eV) neutrons in moderators located close to the target. Current plans are to have two liquid-hydrogen (20-K) moderators and two room-temperature H{sub 2}O moderators. Extensive engineering design work has been conducted on the moderator vessels. For our studies we have produced realistic neutronic representations of these moderators. We report on neutronic studies conducted on these representations of the moderators using Monte Carlo simulation techniques.

Murphy, D.B.

1999-11-14T23:59:59.000Z

37

Validation of a virtual source model for Monte Carlo dose calculations of a flattening filter free linac  

SciTech Connect

Purpose: A linac delivering intensity-modulated radiotherapy (IMRT) can benefit from a flattening filter free (FFF) design which offers higher dose rates and reduced accelerator head scatter than for conventional (flattened) delivery. This reduction in scatter simplifies beam modeling, and combining a Monte Carlo dose engine with a FFF accelerator could potentially increase dose calculation accuracy. The objective of this work was to model a FFF machine using an adapted version of a previously published virtual source model (VSM) for Monte Carlo calculations and to verify its accuracy. Methods: An Elekta Synergy linear accelerator operating at 6 MV has been modified to enable irradiation both with and without the flattening filter (FF). The VSM has been incorporated into a commercially available treatment planning system (Monaco Trade-Mark-Sign v 3.1) as VSM 1.6. Dosimetric data were measured to commission the treatment planning system (TPS) and the VSM adapted to account for the lack of angular differential absorption and general beam hardening. The model was then tested using standard water phantom measurements and also by creating IMRT plans for a range of clinical cases. Results: The results show that the VSM implementation handles the FFF beams very well, with an uncertainty between measurement and calculation of <1% which is comparable to conventional flattened beams. All IMRT beams passed standard quality assurance tests with >95% of all points passing gamma analysis ({gamma} < 1) using a 3%/3 mm tolerance. Conclusions: The virtual source model for flattened beams was successfully adapted to a flattening filter free beam production. Water phantom and patient specific QA measurements show excellent results, and comparisons of IMRT plans generated in conventional and FFF mode are underway to assess dosimetric uncertainties and possible improvements in dose calculation and delivery.

Cashmore, Jason; Golubev, Sergey; Dumont, Jose Luis; Sikora, Marcin; Alber, Markus; Ramtohul, Mark [Hall-Edwards Radiotherapy Research Group, University Hospital Birmingham NHS Foundation Trust, United Kingdom, B15 2TH (United Kingdom); Elekta CMS Software, St. Louis, Missouri 63043 (United States); Department of Oncology and Medical Physics, Haukeland University Hospital, Bergen 5021 (Norway); Section for Biomedical Physics, University Hospital for Radiation Oncology, Hoppe-Seyler-Str 3, 72076, Tuebingen (Germany); Hall-Edwards Radiotherapy Research Group, University Hospital Birmingham NHS Foundation Trust, United Kingdom, B15 2TH (United Kingdom)

2012-06-15T23:59:59.000Z

38

MCNP-DSP calculations of the {sup 252}Cf-source-driven noise analysis measurements of highly enriched uranium metal cylinders  

SciTech Connect

This paper presents calculations of the {sup 252}Cf-source-driven noise analysis measurements for subcritical highly enriched uranium metal cylinders using the Monte Carlo code MCNP-DSP. This code directly calculates the noise analysis data from the {sup 252}Cf- source-driven noise analysis method for both neutron and gamma ray detectors. Direct calculation of experimental observables by the Monte Carlo method allows for the benchmarking of the calculational model and the cross sections and for determining the bias in the calculation.

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

1995-07-01T23:59:59.000Z

39

Nucleon form factors from high statistics mixed-action calculations with 2+1 flavors  

SciTech Connect

We present new high-statistics results for nucleon form factors at pion masses of approximately 290, 350, 500, and 600 MeV using a mixed action of domain wall valence quarks on an improved staggered sea. We perform chiral fits to both vector and axial form factors and compare our results to experiment.

Schroers, Wolfram; Edwards, Robert G; Engelhardt, Michael; Fleming, George Taminga; Hagler, Philipp; Lin, Huey-Wen; Lin, Mei-Feng; Meyer, Harvey B; Musch, Bernhard; Negele, John W; Orginos, Kostas; Pochinsky, Andrew V; Procura, Massimiliano; Renner, Dru B; Richards, David G; Syritsyn, Sergey N

2009-12-01T23:59:59.000Z

40

Current-source charge-pump power-factor-correction electronic ballast  

SciTech Connect

A current-source charge-pump power-factor-correction (CS-CPPFC) electronic ballast is presented in this paper. Unity-power-factor condition and principle of operation using the CP concept are derived and analyzed. Based on the steady-state analysis, the design considerations are discussed in detail. It is shown that the power switch only deals with the resonant load current, which is the same as in the two-stage approach so that small-current rating devices can be used. The developed CS-CPPFC electronic ballast can save one inductor and has a potentially low cost. The CS-CP electronic ballast with switching frequency modulation to improve crest factor is developed, implemented, and tested. It is shown that 0.99 power factor, 11.3% total harmonic distortion (THD), and 1.54 crest factor can be achieved for 85-W fluorescent lamps.

Qian, J.; Lee, F.C.Y. [Virginia Polytechnic Inst. and State Univ., Blacksburg, VA (United States); Yamauchi, Tokushi [Matsushita Electric Works, Inc., Woburn, MA (United States)

1998-05-01T23:59:59.000Z

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


41

Calculation of Fire Severity Factors and Fire Non-Suppression Probabilities For A DOE Facility Fire PRA  

Science Conference Proceedings (OSTI)

Over a 12 month period, a fire PRA was developed for a DOE facility using the NUREG/CR-6850 EPRI/NRC fire PRA methodology. The fire PRA modeling included calculation of fire severity factors (SFs) and fire non-suppression probabilities (PNS) for each safe shutdown (SSD) component considered in the fire PRA model. The SFs were developed by performing detailed fire modeling through a combination of CFAST fire zone model calculations and Latin Hypercube Sampling (LHS). Component damage times and automatic fire suppression system actuation times calculated in the CFAST LHS analyses were then input to a time-dependent model of fire non-suppression probability. The fire non-suppression probability model is based on the modeling approach outlined in NUREG/CR-6850 and is supplemented with plant specific data. This paper presents the methodology used in the DOE facility fire PRA for modeling fire-induced SSD component failures and includes discussions of modeling techniques for: Development of time-dependent fire heat release rate profiles (required as input to CFAST), Calculation of fire severity factors based on CFAST detailed fire modeling, and Calculation of fire non-suppression probabilities.

Tom Elicson; Bentley Harwood; Jim Bouchard; Heather Lucek

2011-03-01T23:59:59.000Z

42

Calculation Package: Derivation of Facility-Specific Derived Air Concentration (DAC) Values in Support of Spallation Neutron Source Operations  

SciTech Connect

Derived air concentration (DAC) values for 175 radionuclides* produced at the Oak Ridge National Laboratory (ORNL) Spallation Neutron Source (SNS), but not listed in Appendix A of 10 CFR 835 (01/01/2009 version), are presented. The proposed DAC values, ranging between 1 E-07 {micro}Ci/mL and 2 E-03 {micro}Ci/mL, were calculated in accordance with the recommendations of the International Commission on Radiological Protection (ICRP), and are intended to support an exemption request seeking regulatory relief from the 10 CFR 835, Appendix A, requirement to apply restrictive DACs of 2E-13 {micro}Ci/mL and 4E-11 {micro}Ci/mL and for non-listed alpha and non-alpha-emitting radionuclides, respectively.

McLaughlin, David A [ORNL

2009-12-01T23:59:59.000Z

43

Power-Factor Calculation under Consideration of Cross Saturation of the Interior Permanent Magnet Synchronous Motor with Brushless Field Excitation  

SciTech Connect

This paper introduces a new method for calculating the power factor with consideration of the cross saturation between the direct-axis (d-axis) and the quadrature-axis (q-axis) of an interior permanent magnet synchronous motor (IPMSM). The conventional two-axis IPMSM model is modified to include the cross-saturation effect by adding the cross-coupled inductance terms. This paper also contains the new method of calculating the cross-coupled inductance values as well as self-inductance values in d- and q-axes. The analyzed motor is a high-speed brushless field excitation machine that offers high torque per ampere per core length at low speed and weakened flux at high speed, which was developed for the traction motor of a hybrid electric vehicle.

Lee, Seong T [ORNL; Burress, Timothy A [ORNL; Hsu, John S [ORNL

2009-01-01T23:59:59.000Z

44

Obtaining oblique technique source-to-skin distances for irregular field (Clarkson) calculations: The Mayo Off-axis Distance Indicator  

Science Conference Proceedings (OSTI)

Significant dose inhomogeneities may exist between the supraclavicular fossa (SCF) and the internal mammary chain (IMC) regions in the irregular L-shaped (hockey stick) field associated with breast cancer treatments. This dose inhomogeneity exists, in part, because of a positive air gap in the SCF and a negative air gap in the IMC locations. Independent of treatment technique, (i.e., whether anterior-posterior (AP) or oblique fields are used), accurate source-to-skin distance (SSD) values for the SCF, IMC, and axilla are necessary when doing an irregular field (Clarkson) dose calculation. However, when an oblique technique is used to treat the hockey stick field, obtaining non-central-axis SSDs is not as straightforward as when an AP technique is employed. The Mayo Off-axis Distance Indicator was constructed to slide into the blocking tray slot of the simulator or treatment machine. This mechanical measuring device provides quick and accurate SSD measurements for non-central-axis points under either AP or, more importantly, oblique treatment conditions.

Lajoie, W.N. (Mayo Medical Center, Rochester, MN (USA))

1988-09-01T23:59:59.000Z

45

Sources  

NLE Websites -- All DOE Office Websites (Extended Search)

SOURCES Microsoft Corporation. "Gasohol," Microsoft Encarta Online Encyclopedia 2001, http:encarta.msn.com. U.S. Department of Transportation, Federal Highway Administration, A...

46

Spallation Neutron Source Availability Top-Down Apportionment Using Characteristic Factors and Expert Opinion  

SciTech Connect

Apportionment is the assignment of top-level requirements to lower tier elements of the overall facility. A method for apportioning overall facility availability requirements among systems and subsystems is presented. Characteristics that influence equipment reliability and maintainability are discussed. Experts, using engineering judgment, scored each characteristic for each system whose availability design goal is to be established. The Analytic Hierarchy Process (AHP) method is used to produce a set of weighted rankings for each characteristic for each alternative system. A mathematical model is derived which incorporates these weighting factors. The method imposes higher availability requirements on those systems in which an incremental increase in availability is easier to achieve, and lower availability requirements where greater availability is more difficult and costly. An example is given of applying this top-down apportionment methodology to the Spallation Neutron Source (SNS) facility.

Haire, M.J.; Schryver, J.C.

1999-10-01T23:59:59.000Z

47

Calculation of Airflow over an Isolated Heat Source with Application to the Dynamics of V-Shaped Clouds  

Science Conference Proceedings (OSTI)

The stably stratified airflow over a three-dimensional elevated heat source is investigated using the linearized equations of motion. A low-level upward motion can be produced for airflow over a prescribed, isolated heat source for a wide variety ...

Yuh-Lang Lin

1986-11-01T23:59:59.000Z

48

Dynamical mass generation by source inversion: calculating the mass gap of the chiral Gross-Neveu model  

E-Print Network (OSTI)

We probe the U(N) chiral Gross-Neveu model with a source-term $J\\l{\\Psi}\\Psi$. We find an expression for the renormalization scheme and scale invariant source $\\hat{J}$, as a function of the generated mass gap. The expansion of this function is organized in such a way that all scheme and scale dependence is reduced to one single parameter $d$. We obtain a non-perturbative mass gap as the solution of $\\hat{J}=0$. A physical choice for $d$ gives good results for $N>2$. The self-consistent minimal sensitivity condition gives a slight improvement.

K. Van Acoleyen; J. A. Gracey; H. Verschelde

2002-02-27T23:59:59.000Z

49

Supplement D to compilation of air pollutant emission factors. Volume 1: Stationary point and area sources (fifth edition)  

SciTech Connect

This document contains emission factors and process information for more than 200 air pollution source categories. These emission factors have been compiled from source test data, material balance studies, and they can be used judiciously in making emission estimations for various purposes. This supplement to AP-42 addresses pollutant-generating activity from natural gas combustion, wood waste combustion in boilers; municipal solid waste landfills; waste water collection, treatment and storage; organic liquid storage tanks; nitric acid; grain elevators and processes; plywood manufacturing; lime manufacturing; primary aluminum production; paved roads; abrasive blasting; enteric fermentation -- greenhouse gases.

NONE

1998-08-31T23:59:59.000Z

50

Journal of Power Sources xxx (2005) xxxxxx Vehicle-to-grid power fundamentals: Calculating capacity and net revenue  

E-Print Network (OSTI)

As the light vehicle fleet moves to electric drive (hybrid, battery, and fuel cell vehicles), an opportunity opens for vehicle-to-grid (V2G) power. This article defines the three vehicle types that can produce V2G power, and the power markets they can sell into. V2G only makes sense if the vehicle and power market are matched. For example, V2G appears to be unsuitable for baseload powerthe constant round-theclock electricity supplybecause baseload power can be provided more cheaply by large generators, as it is today. Rather, V2Gs greatest near-term promise is for quick-response, high-value electric services. These quick-response electric services are purchased to balance constant fluctuations in load and to adapt to unexpected equipment failures; they account for 510 % of electric cost $ 12 billion per year in the US. This article develops equations to calculate the capacity for grid power from three types of electric drive vehicles. These equations are applied to evaluate revenue and costs for these vehicles to supply electricity to three electric markets (peak power, spinning reserves, and regulation). The results suggest that the engineering rationale and economic motivation for V2G power are compelling. The societal advantages of developing V2G include an additional revenue stream for cleaner vehicles, increased stability and reliability of the electric grid, lower electric system costs, and eventually, inexpensive storage and backup for renewable electricity.

Willett Kempton; Jasna Tomi?

2004-01-01T23:59:59.000Z

51

Compilation of Diversity Factors and Schedules for Energy and Cooling Load Calculations, ASHRAE Research Project 1093, Preliminary Report, Literature Review and Database Search  

E-Print Network (OSTI)

In this report, the first report for the ASHRAE 1093-RP project, we present: (1) our extended literature search of methods used to derive load shapes and diversity factors in the U.S. and Europe, (2) a survey of available databases of monitored commercial end-use electrical data in the U.S. and Europe, and (3) a review of classification schemes of the commercial building stock listed in national standards and codes, and reported by researchers and utility projects. The findings in this preliminary report will help us in performing the next steps of the project where we will identify and test appropriate daytyping methods on relevant monitored data sets of lighting and equipment (and other surrogates for occupancy) to develop a library of diversity factors and schedules for use in energy and cooling load simulations. The goal of this project is to compile a library of schedules and diversity factors for energy and cooling load calculations in various types of indoor office environments in the U.S. and Europe. Two sets of diversity factors, one for peak cooling load calculations and one for energy calculations will be developed.

Abushakra, B.; Haberl, J. S.; Claridge, D. E.

1999-05-01T23:59:59.000Z

52

Pacific Northwest National Laboratory Site Dose-per-Unit-Release Factors for Use in Calculating Radionuclide Air Emissions Potential-to-Emit Doses  

Science Conference Proceedings (OSTI)

This report documents assumptions and inputs used to prepare the dose-per-unit-release factors for the Pacific Northwest National Laboratory (PNNL) Site (including the buildings that make up the Physical Sciences Facility [PSF] as well as the Environmental Molecular Sciences Laboratory [EMSL]) calculated using the EPA-approved Clean Air Act Assessment Package 1988Personal Computer (CAP88-PC) Version 3 software package. The dose-per-unit-release factors are used to prepare dose estimates for a maximum public receptor (MPR) in support of Radioactive Air Pollutants Notice of Construction (NOC) applications for the PNNL Site.

Barnett, J. M.; Rhoads, Kathleen

2009-06-11T23:59:59.000Z

53

Numerical Simulation of a Displacement Ventilation System with Multi-heat Sources and Analysis of Influential Factors  

E-Print Network (OSTI)

Displacement ventilation (DV) is a promising ventilation concept due to its high ventilation efficiency. In this paper, the application of the CFD method, the velocity and temperature fields of three-dimensional displacement ventilation systems with double heat sources are numerically simulated. The model is verified by experimental data. The results of the study show that thermal stratification characteristics exist in indoor temperature fields. The paper also analyzes the influence of different influential factors, e.g., the distance between heat sources, temperature of heat source, heat characteristics of the wall and outdoor temperature. It was found that the human requirement for comfort is satisfied easily when the distance between heat sources is long. Under the conditions simulated in this paper, when the distance was more than 0.8m, the temperature distribution tended to be average and steady, and it did not change as the distance changed. Second, the temperature change of the thermal current has a large influence on the indoor temperature. The rise in thermal current temperature makes the vertical temperature gradient in the room increase. The upper temperature of the room becomes higher, as does the height of the high temperature air level that lies in the upper part of the room. Finally, both the heat loss of the surrounding structure and the change in outdoor temperature have a large influence on indoor temperature. However, it does not influence the thermal stratification characteristics of DV. The only thing that has changed is the thermal stratification height.

Wu, X.; Gao, J.; Wu, W.

2006-01-01T23:59:59.000Z

54

Investigation of the factors determining the modulation characteristics of gas-discharge IR sources  

Science Conference Proceedings (OSTI)

The effect of design parameters and voltage of pulsed cesium sources with sapphire envelopes on their modulation characteristics are considered for the following combinations of operating parameters: the average repetition rate of current pulses up to f{sub i} = 1.0 kHz and the consumed electric power up to P{sub l} = 3 kW for the spectral range 3-5 {mu}m; f{sub i} = 1.0-8.0 kHz and P{sub l} up to 1.0 kW for the spectral range 0.8-2.7 {mu}m. Recommendations on further improvement of the modulation characteristics of lamps are given.

Gavrish, S. V.; Zhmaev, V. S.; Kobzar, A. I.; Loginov, V. V. [ZENITH Special Design Bureau, STELLA Factory (Russian Federation)

2010-12-15T23:59:59.000Z

55

Compilation of Diversity Factors and Schedules for Energy and Cooling Load Calculations, Phase II Report - Identified Relevant Data Sets, Methods, and Variability Analysis  

E-Print Network (OSTI)

This is the second report of the ASHRAE 1093-RP project that reports on the progress during the scheduled Phase II effort. In this report, we present: (1) the data sets identified and acquired required for the analysis; (2) the method adopted for classifying the Office building categories; (3) the relevant methods for daytyping necessary for creating the typical load shapes for energy and cooling load calculation; (4) the relevant robust variability (uncertainty) analysis; (5) typical load shapes reported in the literature; (6) a test to assure the non-weather dependency (seasonal variation) of the lighting and equipment data sets; and (7) a proposed occupancy surrogate variable. The results obtained during Phase II will enable us to proceed with Phase III, as planned. Phase III will cover: (1) developing the typical load shapes for the acquired data sets, using the proposed method, for both energy and cooling load calculations; (2) developing the tool-kit for deriving the new diversity factors and general guidelines for their use; and (3) developing illustrative examples of the use of the diversity factors in the DOE-2 and BLAST simulation programs.

Abushakra, B.; Haberl, J. S.; Claridge, D. E.

1999-01-01T23:59:59.000Z

56

Design Calculations For APS Safety Shutters  

NLE Websites -- All DOE Office Websites (Extended Search)

9 Design Calculations for the Advanced Photon Source Safety Shutters P. K. Job, Advanced Photon Source B. J. Micklich, Intense Pulsed Neutron Source Argonne National Laboratory,...

57

Evaluated teletherapy source library  

DOE Patents (OSTI)

The Evaluated Teletherapy Source Library (ETSL) is a system of hardware and software that provides for maintenance of a library of useful phase space descriptions (PSDs) of teletherapy sources used in radiation therapy for cancer treatment. The PSDs are designed to be used by PEREGRINE, the all-particle Monte Carlo dose calculation system. ETSL also stores other relevant information such as monitor unit factors (MUFs) for use with the PSDs, results of PEREGRINE calculations using the PSDs, clinical calibration measurements, and geometry descriptions sufficient for calculational purposes. Not all of this information is directly needed by PEREGRINE. It also is capable of acting as a repository for the Monte Carlo simulation history files from which the generic PSDs are derived.

Cox, Lawrence J. (Los Alamos, NM); Schach Von Wittenau, Alexis E. (Livermore, CA)

2000-01-01T23:59:59.000Z

58

Power-Factor and Torque Calculation under Consideration of Cross Saturation of the Interior Permanent Magnet Synchronous Motor with Brushless Field Excitation  

SciTech Connect

This paper introduces a new method for calculating the power factor and output torque by considering the cross saturation between direct-axis (d-axis) and quadrature-axis (q-axis) of an interior permanent magnet synchronous motor (IPMSM). The conventional two-axis IPMSM model is modified to include the cross saturation effect by adding the cross-coupled inductance terms. This paper also contains the new method of calculating the cross-coupled inductance values as well as self-inductance values in d- and q-axes. The analyzed motor is a high-speed brushless field excitation machine that offers high torque per ampere per core length at low speed and weakened flux at high speed, which was developed for the traction motor of a hybrid electric vehicle. The conventional two-axis IPMSM model was modified to include the cross-saturation effect by adding the cross-coupled inductance terms Ldq and Lqd. By the advantage of the excited structure of the experimental IPMSM, the analyzing works were performed under two conditions, the highest and lowest excited conditions. Therefore, it is possible to investigate the cross-saturation effect when a machine has higher magnetic flux from its rotor. The following is a summary of conclusions that may be drawn from this work: (1) Considering cross saturation of an IPMSM offers more accurate expected values of motor parameters in output torque calculation, especially when negative d-axis current is high; (2) A less saturated synchronous machine could be more affected by the cross-coupled saturation effect; (3) Both cross-coupled inductances, L{sub qd} and L{sub dq}, are mainly governed by d-axis current rather than q-axis current; (4) The modified torque equation, can be used for the dynamic model of an IPMSM for developing a better control model or control strategy; and (5) It is possible that the brushless field excitation structure has a common magnetic flux path on both d- and q-axis, and as a result, the reluctance torque of the machine could be reduced.

Lee, Seong T [ORNL; Burress, Timothy A [ORNL; Tolbert, Leon M [ORNL

2009-01-01T23:59:59.000Z

59

Graphics Calculators In Developmental MathematicsPolicies And Practice: An Investigation Of Factors Affecting Instructors Classroom Usage In Tennessee Community Colleges.  

E-Print Network (OSTI)

??The purpose of this study was to investigate the frequency of Tennessee community college full-time developmental mathematics instructors classroom graphics calculator usage (percent of class (more)

Smith, Joyce Petty

2006-01-01T23:59:59.000Z

60

Producing persistent, high-current, high-duty-factor H{sup -} beams for routine 1 MW operation of Spallation Neutron Source (invited)  

Science Conference Proceedings (OSTI)

Since 2009, the Spallation Neutron Source (SNS) has been producing neutrons with ion beam powers near 1 MW, which requires the extraction of {approx}50 mA H{sup -} ions from the ion source with a {approx}5% duty factor. The 50 mA are achieved after an initial dose of {approx}3 mg of Cs and heating the Cs collar to {approx}170 deg. C. The 50 mA normally persist for the entire 4-week source service cycles. Fundamental processes are reviewed to elucidate the persistence of the SNS H{sup -} beams without a steady feed of Cs and why the Cs collar temperature may have to be kept near 170 deg. C.

Stockli, Martin P.; Han, B. X.; Hardek, T. W.; Kang, Y. W.; Murray, S. N.; Pennisi, T. R.; Piller, C.; Santana, M.; Welton, R. [Spallation Neutron Source, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831 (United States)

2012-02-15T23:59:59.000Z

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


61

Footprint Calculator?  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

fuels and advanced vehicles (AFVs). The Greenhouse gases, Regulated Emis- sions, and Energy use in Transportation (GREET) Fleet Foot- print Calculator can help fleets decide on...

62

Calculators for Estimating Greenhouse Gas Emissions from Public  

NLE Websites -- All DOE Office Websites (Extended Search)

CALCULATORS Tables 1 and 2 list the GHG emissions calculators found by a literature search of published sources. The literature search for calculators was conducted through...

63

Plutonium 239 Equivalency Calculations  

SciTech Connect

This document provides the basis for converting actual weapons grade plutonium mass to a plutonium equivalency (PuE) mass of Plutonium 239. The conversion can be accomplished by performing calculations utilizing either: (1) Isotopic conversions factors (CF{sub isotope}), or (2) 30-year-old weapons grade conversion factor (CF{sub 30 yr}) Both of these methods are provided in this document. Material mass and isotopic data are needed to calculate PuE using the isotopic conversion factors, which will provide the actual PuE value at the time of calculation. PuE is the summation of the isotopic masses times their associated isotopic conversion factors for plutonium 239. Isotopic conversion factors are calculated by a normalized equation, relative to Plutonium 239, of specific activity (SA) and cumulated dose inhalation affects based on 50-yr committed effective dose equivalent (CEDE). The isotopic conversion factors for converting weapons grade plutonium to PuE are provided in Table-1. The unit for specific activity (SA) is curies per gram (Ci/g) and the isotopic SA values come from reference [1]. The cumulated dose inhalation effect values in units of rem/Ci are based on 50-yr committed effective dose equivalent (CEDE). A person irradiated by gamma radiation outside the body will receive a dose only during the period of irradiation. However, following an intake by inhalation, some radionuclides persist in the body and irradiate the various tissues for many years. There are three groups CEDE data representing lengths of time of 0.5 (D), 50 (W) and 500 (Y) days, which are in reference [2]. The CEDE values in the (W) group demonstrates the highest dose equivalent value; therefore they are used for the calculation.

Wen, J

2011-05-31T23:59:59.000Z

64

The California Climate Action Registry: Development of methodologies for calculating greenhouse gas emissions from electricity generation  

E-Print Network (OSTI)

draft). Estimating Carbon Dioxide Emission Factors for theemissions factors for calculating the combined net carbon dioxide

2002-01-01T23:59:59.000Z

65

Development of methodologies for calculating greenhouse gas emissions from electricity generation for the California climate action registry  

E-Print Network (OSTI)

draft). Estimating Carbon Dioxide Emission Factors for theemissions factors for calculating the combined net carbon dioxide

2002-01-01T23:59:59.000Z

66

Validating analysis methodologies used in burnup credit criticality calculations  

Science Conference Proceedings (OSTI)

The concept of allowing reactivity credit for the depleted (or burned) state of pressurized water reactor fuel in the licensing of spent fuel facilities introduces a new challenge to members of the nuclear criticality community. The primary difference in this analysis approach is the technical ability to calculate spent fuel compositions (or inventories) and to predict their effect on the system multiplication factor. Isotopic prediction codes are used routinely for in-core physics calculations and the prediction of radiation source terms for both thermal and shielding analyses, but represent an innovation for criticality specialists. This paper discusses two methodologies currently being developed to specifically evaluate isotopic composition and reactivity for the burnup credit concept. A comprehensive approach to benchmarking and validating the methods is also presented. This approach involves the analysis of commercial reactor critical data, fuel storage critical experiments, chemical assay isotopic data, and numerical benchmark calculations.

Brady, M.C. [Oak Ridge National Lab., TN (United States); Napolitano, D.G. [Yankee Atomic Electric Co., Boston, MA (United States)

1992-02-01T23:59:59.000Z

67

Neutron Thermal Cross Sections, Westcott Factors, Resonance Integrals, Maxwellian Averaged Cross Sections and Astrophysical Reaction Rates Calculated from the ENDF/B-VII.1, JEFF-3.1.2, JENDL-4.0, ROSFOND-2010, CENDL-3.1 and EAF-2010 Evaluated Data Libraries  

Science Conference Proceedings (OSTI)

We present calculations of neutron thermal cross sections, Westcott factors, resonance integrals, Maxwellian-averaged cross sections and astrophysical reaction rates for 843 ENDF materials using data from the major evaluated nuclear libraries and European activation file. Extensive analysis of newly-evaluated neutron reaction cross sections, neutron covariances, and improvements in data processing techniques motivated us to calculate nuclear industry and neutron physics quantities, produce s-process Maxwellian-averaged cross sections and astrophysical reaction rates, systematically calculate uncertainties, and provide additional insights on currently available neutron-induced reaction data. Nuclear reaction calculations are discussed and new results are presented. Due to space limitations, the present paper contains only calculated Maxwellian-averaged cross sections and their uncertainties. The complete data sets for all results are published in the Brookhaven National Laboratory report.

Pritychenko, B. [National Nuclear Data Center, Brookhaven National Laboratory, Upton, NY 11973-5000 (United States)] [National Nuclear Data Center, Brookhaven National Laboratory, Upton, NY 11973-5000 (United States); Mughabghab, S.F. [National Nuclear Data Center, Brookhaven National Laboratory, Upton, NY 11973-5000 (United States)] [National Nuclear Data Center, Brookhaven National Laboratory, Upton, NY 11973-5000 (United States)

2012-12-15T23:59:59.000Z

68

My Trip Calculator  

NLE Websites -- All DOE Office Websites (Extended Search)

Savings Calculator Trip Calculator Benefits Why is fuel economy important? Climate Change Oil Dependence Costs Sustainability Save Money Vehicles produce about half of the...

69

Dose-rate conversion factors for external exposure to photons and electrons  

SciTech Connect

Dose-rate conversion factors for external exposure to photons and electrons have been calculated for approximately 500 radionuclides of potential importance in environmental radiological assessments. The dose-rate factors were obtained using the DOSFACTER computer code. The results given in this report incorporate calculation of electron dose-rate factors for radiosensitive tissues of the skin, improved estimates of organ dose-rate factors for photons, based on organ doses for monoenergetic sources at the body surface of an exposed individual, and the spectra of scattered photons in air from monoenergetic sources in an infinite, uniformly contaminated atmospheric cloud, calculation of dose-rate factors for other radionuclides in addition to those of interest in the nuclear fuel cycle, and incorporation of updated radioactive decay data for all radionuclides. Dose-rate factors are calculated for three exposure modes - immersion in contaminated air, immersion in contaminated water, and exposure at a height of 1 m above a contaminated ground surface. The report presents the equations used to calculate the external dose-rate factors for photons and electrons, documentation of the revised DOSFACTER computer code, and a complete tabulation of the calculated dose-rate factors. 30 refs., 12 figs.

Kocher, D.C.

1981-08-01T23:59:59.000Z

70

FLAG-SGH Sedov calculations  

SciTech Connect

We did not run with a 'cylindrically painted region'. However, we did compute two general variants of the original problem. Refinement studies where a single zone at each level of refinement contains the entire internal energy at t=0 or A 'finite' energy source which has the same physical dimensions as that for the 91 x 46 mesh, but consisting of increasing numbers of zones with refinement. Nominal mesh resolution: 91 x 46. Other mesh resolutions: 181 x 92 and 361 x 184. Note, not identical to the original specification. To maintain symmetry for the 'fixed' energy source, the mesh resolution was adjusted slightly. FLAG Lagrange or full (Eulerian) ALE was used with various options for each simulation. Observation - for either Lagrange or ALE, point or 'fixed' source, calculations converge on density and pressure with mesh resolution, but not energy, (not vorticity either).

Fung, Jimmy [Los Alamos National Laboratory; Schofield, Sam [LLNL; Shashkov, Mikhail J. [Los Alamos National Laboratory

2012-06-25T23:59:59.000Z

71

R-value Calculator  

NLE Websites -- All DOE Office Websites (Extended Search)

Advanced Wall Systems Advanced Wall Systems ORNL Home ASTM Testing BEP Home Related Sites Work With Us Advanced Wall Systems Home Interactive Calculators New Whole Wall R-value Calculators As A Part Of The ORNL Material Database For Whole Building Energy Simulations These calculators are replacing the old Whole Wall Thermal Performance calculator. These new versions of the calculator contain many new features and are part of the newly developed Interactive Envelope Materials Database for Whole-Building Energy Simulation Programs. The simple version of the Whole Wall R-value calculator is now available for use. This calculator is similar to the previous Whole Wall Thermal Performance calculator and does not require any downloads from the user. However, it was updated to allow calculations for fourteen wall details

72

Definition: Interchange Distribution Calculator | Open Energy Information  

Open Energy Info (EERE)

Distribution Calculator Distribution Calculator Jump to: navigation, search Dictionary.png Interchange Distribution Calculator The mechanism used by Reliability Coordinators in the Eastern Interconnection to calculate the distribution of Interchange Transactions over specific Flowgates. It includes a database of all Interchange Transactions and a matrix of the Distribution Factors for the Eastern Interconnection.[1] Related Terms Reliability Coordinator, Interchange Transaction References ↑ Glossary of Terms Used in Reliability Standards An i LikeLike UnlikeLike You like this.Sign Up to see what your friends like. nline Glossary Definition Retrieved from "http://en.openei.org/w/index.php?title=Definition:Interchange_Distribution_Calculator&oldid=480261" Categories: Definitions

73

The California Climate Action Registry: Development of methodologies for calculating greenhouse gas emissions from electricity generation  

E-Print Network (OSTI)

draft). Estimating Carbon Dioxide Emission Factors for thefactors for calculating the combined net carbon dioxide

2002-01-01T23:59:59.000Z

74

Bayesian Radiation Source Localization  

Science Conference Proceedings (OSTI)

Locating illicit radiological sources using gamma ray or neutron detection is a key challenge for both homeland security and nuclear nonproliferation. Localization methods using an array of detectors or a sequence of observations in time and space must provide rapid results while accounting for a dynamic attenuating environment. In the presence of significant attenuation and scatter, more extensive numerical transport calculations in place of the standard analytical approximations may be required to achieve accurate results. Numerical adjoints based on deterministic transport codes provide relatively efficient detector response calculations needed to determine the most likely location of a true source. Probabilistic representations account for uncertainty in the source location resulting from uncertainties in detector responses, the approximations that are used, and the potential for nonunique solutions. A Bayesian approach improves on previous likelihood methods for source localization by allowing the incorporation of all available information to help constrain solutions.

Jarman, Kenneth D.; Miller, Erin A.; Wittman, Richard S.; Gesh, Christopher J.

2011-07-01T23:59:59.000Z

75

New Optical Evaluation Approach for Parabolic Trough Collectors: First-Principle OPTical Intercept Calculation  

SciTech Connect

A new analytical method -- First-principle OPTical Intercept Calculation (FirstOPTIC) -- is presented here for optical evaluation of trough collectors. It employs first-principle optical treatment of collector optical error sources and derives analytical mathematical formulae to calculate the intercept factor of a trough collector. A suite of MATLAB code is developed for FirstOPTIC and validated against theoretical/numerical solutions and ray-tracing results. It is shown that FirstOPTIC can provide fast and accurate calculation of intercept factors of trough collectors. The method makes it possible to carry out fast evaluation of trough collectors for design purposes. The FirstOPTIC techniques and analysis may be naturally extended to other types of CSP technologies such as linear-Fresnel collectors and central-receiver towers.

Zhu, G.; Lewandowski, A.

2012-11-01T23:59:59.000Z

76

Power Line Calculator for DOS  

Science Conference Proceedings (OSTI)

The Power Line Calculator (PLC) for DOS, version 1.0, is a program that describes the electrical characteristics of a transmission or distribution system given user-defined input. This input may consist of a combination of operating currents and phases, symmetric components, power factor, and real or reactive power. The program also allows the user to designate whether currents are present on the system neutral or in the ground. The PLC assumes that any value entered by the user remains fixed (e.g., phase current, power factor), and for underdetermined systems, basic default assumptions are incorporated: the power factor is held at or near 1.0, the net phase current is kept at or near zero, and the phase conductor currents are kept balanced. The program operates under PC/MS-DOS version 3.3 or later, and the output is available in both tabular and graphic formats.

Silva, J.M. (Enertech Consultants, Campbell, CA (United States))

1992-11-01T23:59:59.000Z

77

Oceanic Heat Flux Calculation  

Science Conference Proceedings (OSTI)

The authors review the procedure for the direct calculation of oceanic heat flux from hydrographic measurements and set out the full recipe that is required.

Sheldon Bacon; Nick Fofonoff

1996-12-01T23:59:59.000Z

78

Scattering Length Density Calculator  

Science Conference Proceedings (OSTI)

... For energy dependent cross sections please go to ... The neutron scattering length density is defined ... To calculate scattering length densities enter a ...

79

Heating Fuel Comparision Calculator  

U.S. Energy Information Administration (EIA)

Wood, Pellet, Corn (kernel), and Coal Heaters Heating Fuel Comparison Calculator Instructions and Guidance Residential Fuel/Energy Price Links Spot Prices, Daily

80

Scattering Length Density Calculator  

Science Conference Proceedings (OSTI)

... The first calculation will take the longest because the program has to download ... will take a few seconds as the database of isotopes is downloaded ...

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


81

Multiphase flow calculation software  

DOE Patents (OSTI)

Multiphase flow calculation software and computer-readable media carrying computer executable instructions for calculating liquid and gas phase mass flow rates of high void fraction multiphase flows. The multiphase flow calculation software employs various given, or experimentally determined, parameters in conjunction with a plurality of pressure differentials of a multiphase flow, preferably supplied by a differential pressure flowmeter or the like, to determine liquid and gas phase mass flow rates of the high void fraction multiphase flows. Embodiments of the multiphase flow calculation software are suitable for use in a variety of applications, including real-time management and control of an object system.

Fincke, James R. (Idaho Falls, ID)

2003-04-15T23:59:59.000Z

82

SUPPORTING CALCULATIONS FOR SUBMERGED BED SCRUBBER CONDENSATE DISPOSAL PRECONCEPTUAL STUDY  

Science Conference Proceedings (OSTI)

This document provides supporting calculations for the preparation of the Submerged Bed Scrubber Condensate Disposal Pre conceptual Study report The supporting calculations include equipment sizing, Hazard Category determination, and LAW Melter Decontamination Factor Adjustments.

PAJUNEN AL; TEDESCHI AR

2012-09-18T23:59:59.000Z

83

Supporting Calculations For Submerged Bed Scrubber Condensate Disposal Preconceptual Study  

SciTech Connect

This document provides supporting calculations for the preparation of the Submerged Bed Scrubber Condensate Disposal Preconceptual Study report The supporting calculations include equipment sizing, Hazard Category determination, and LAW Melter Decontamination Factor Adjustments.

Pajunen, A. J.; Tedeschi, A. R.

2012-09-18T23:59:59.000Z

84

Sources - CECM  

E-Print Network (OSTI)

help annotate Contents Next: References Up: RamanujanModular Equations, Previous: Ramanujan's sum. Sources. [Annotate] [Shownotes]. References [7]...

85

Neutron Activation Calculator  

Science Conference Proceedings (OSTI)

... and incoherent scattering cross sections). Source neutrons (Ang, meV or m/s), Density (g/cm 3 or lattice), Thickness (cm). ...

86

Anisotropy Factors for a 252Cf Source  

Science Conference Proceedings (OSTI)

Neutron Measurements / Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (Part 2) / Radiation Protection

K. G. Veinot; J. S. Bogard

87

Vehicle Cost Calculator  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Electric Plug-in Hybrid Electric Natural Gas (CNG) Flex Fuel (E85) Biodiesel (B20) Next Vehicle Cost Calculator U.S. Department of Energy Energy Efficiency and Renewable Energy...

88

MODIFIED ZONE METHOD CALCULATOR  

NLE Websites -- All DOE Office Websites (Extended Search)

Zone Method is recommended for R-value calculations in steel stud walls by the 1997 ASHRAE Handbook of Fundamentals ASHRAE 1997. The Modified Zone Method is similar to the...

89

Ion source  

DOE Patents (OSTI)

A magnetic filter for an ion source reduces the production of undesired ion species and improves the ion beam quality. High-energy ionizing electrons are confined by the magnetic filter to an ion source region, where the high-energy electrons ionize gas molecules. One embodiment of the magnetic filter uses permanent magnets oriented to establish a magnetic field transverse to the direction of travel of ions from the ion source region to the ion extraction region. In another embodiment, low energy 16 eV electrons are injected into the ion source to dissociate gas molecules and undesired ion species into desired ion species.

Leung, Ka-Ngo (Hercules, CA); Ehlers, Kenneth W. (Alamo, CA)

1984-01-01T23:59:59.000Z

90

Development of methodologies for calculating greenhouse gas emissions from electricity generation for the California climate action registry  

E-Print Network (OSTI)

draft). Estimating Carbon Dioxide Emission Factors for thefactors for calculating the combined net carbon dioxide

2002-01-01T23:59:59.000Z

91

The California Climate Action Registry: Development of methodologies for calculating greenhouse gas emissions from electricity generation  

SciTech Connect

The California Climate Action Registry, which will begin operation in Fall 2002, is a voluntary registry for California businesses and organizations to record annual greenhouse gas emissions. Reporting of emissions in the Registry by a participant involves documentation of both ''direct'' emissions from sources that are under the entity's control and ''indirect'' emissions controlled by others. Electricity generated by an off-site power source is considered to be an indirect emission and must be included in the entity's report. Published electricity emissions factors for the State of California vary considerably due to differences in whether utility-owned out-of-state generation, non-utility generation, and electricity imports from other states are included. This paper describes the development of three methods for estimating electricity emissions factors for calculating the combined net carbon dioxide emissions from all generating facilities that provide electricity to Californians. We find that use of a statewide average electricity emissions factor could drastically under- or over-estimate an entity's emissions due to the differences in generating resources among the utility service areas and seasonal variations. In addition, differentiating between marginal and average emissions is essential to accurately estimate the carbon dioxide savings from reducing electricity use. Results of this work will be taken into consideration by the Registry when finalizing its guidance for use of electricity emissions factors in calculating an entity's greenhouse gas emissions.

Price, Lynn; Marnay, Chris; Sathaye, Jayant; Muritshaw, Scott; Fisher, Diane; Phadke, Amol; Franco, Guido

2002-08-01T23:59:59.000Z

92

TVDG LET Calculator  

NLE Websites -- All DOE Office Websites (Extended Search)

To The B N L Tandem Van de Graaff Accelerator To The B N L Tandem Van de Graaff Accelerator TVDG LET Calculator This program calculates the Peak LET, Corresponding Energy and Range as well as the LET and Range at the Specified Energy for the Specified Ion in the Specified Target. Select the Target Material from the dropdown list. Select the Ion Specie from the dropdown list. Enter the Total Ion Energy in the text box. This is equal to the Atomic Mass times the Energy/Nucleon. Click the 'Calculate' button or press the 'Enter' key. The Peak LET, Corresponding Energy and Range as well as the LET and Range at the Specified Energy for the Specified Ion in the Specified Target will be returned. Select your Target from the list Air Aluminum Oxide Carbon Copper Gallium Arsenide Gold Polyester Polyethylene Silicon Silicon Dioxide Skin Soda Lime Glass Sodium Iodide Water Select your Ion from the list

93

Solar Reflectance Index Calculator  

NLE Websites -- All DOE Office Websites (Extended Search)

Reflectance Index Calculator Reflectance Index Calculator ASTM Designation: E 1980-01 Enter A State: Select a state Alabama Alaska Arkansas Arizona California Colorado Connecticut Delaware Florida Georgia Hawaii Iowa Idaho Illinois Indiana Kansas Kentucky Louisiana Maine Maryland Massachusetts Michigan Minnesota Mississippi Missouri Montana North Carolina North Dakota Nebraska Nevada New Hampshire New Jersey New Mexico New York Ohio Oklahoma Oregon Pennsylvania Pacific Islands Puerto Rico Rhode Island South Carolina South Dakota Tennessee Texas Utah Vermont Virginia Washington Wisconsin West Virginia Wyoming Canadian Cities Enter A City: Select a city Wind Speed (mph) Wind Speed (m/s) Please input both the SR and the TE and the convection coeficient and surface temperature will be calculated

94

Microsoft Word - LS-324 - Equivalent Circuit Model & Power Calculations - DRAFT.doc  

NLE Websites -- All DOE Office Websites (Extended Search)

EQUIVALENT CIRCUIT MODEL AND POWER CALCULATIONS EQUIVALENT CIRCUIT MODEL AND POWER CALCULATIONS FOR THE APS SPX CRAB CAVITIES T. Berenc 1/26/2011 Abstract An equivalent parallel resistor-inductor-capacitor (RLC) circuit with beam loading for a polarized TM 110 dipole-mode cavity is developed and minimum radio- frequency (rf) generator requirements are calculated for the Advanced Photon Source (APS) short-pulse x-ray (SPX) superconducting rf (SRF) crab cavities. INTRODUCTION The polarized TM 110 dipole-mode loss parameter is defined as [1]: U y V Q y R q U y k Z r loss 4 ) ( 2 ) ( ) ( 2 ) 1 ( 2      , (1) where ) ( ) 1 ( y R is the shunt resistance of the dipole-mode transverse wake impedance, U loss is the energy lost to the dipole-mode by charge q with vertical offset y, Q is the loaded quality factor of the cavity, and

95

Spin resonance strength calculations  

SciTech Connect

In calculating the strengths of depolarizing resonances it may be convenient to reformulate the equations of spin motion in a coordinate system based on the actual trajectory of the particle, as introduced by Kondratenko, rather than the conventional one based on a reference orbit. It is shown that resonance strengths calculated by the conventional and the revised formalisms are identical. Resonances induced by radiofrequency dipoles or solenoids are also treated; with rf dipoles it is essential to consider not only the direct effect of the dipole but also the contribution from oscillations induced by it.

Courant,E.D.

2008-10-06T23:59:59.000Z

96

Competitive Sourcing  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

COMPETITIVE SOURCING COMPETITIVE SOURCING ▬▬▬▬▬▬▬▬▬▬▬▬▬▬▬▬▬▬▬▬▬▬▬▬▬▬▬▬▬▬▬▬ Report on Competitive Sourcing Results Fiscal Year 2006 May 2007 Executive Office of the President Office of Management and Budget TABLE OF CONTENTS Executive Summary ...................................................................................... 1 Introduction................................................................................................. 4 I. The big picture ......................................................................................... 4 II. How public-private competition was used in FY 2006 .................................... 6 A. Anticipated benefits from competition in FY 2006

97

Design Factors That Influence Corrosion  

Science Conference Proceedings (OSTI)

Table 3   Corrosion factors that can influence design considerations...Inhibitors Inspection Planned maintenance Source: Ref 25...

98

Examinations of electron temperature calculation methods in Thomson scattering diagnostics  

Science Conference Proceedings (OSTI)

Electron temperature from Thomson scattering diagnostic is derived through indirect calculation based on theoretical model. {chi}-square test is commonly used in the calculation, and the reliability of the calculation method highly depends on the noise level of input signals. In the simulations, noise effects of the {chi}-square test are examined and scale factor test is proposed as an alternative method.

Oh, Seungtae; Lee, Jong Ha; Wi, Hanmin [National Fusion Research Institute, 113 Gwahangno, Yuseong-gu, Daejeon 305-333 (Korea, Republic of)

2012-10-15T23:59:59.000Z

99

Mitigation Efforts Calculator (MEC)  

Science Conference Proceedings (OSTI)

The Mitigation Efforts Calculator (MEC) has been developed by the International Institute for Applied Systems Analysis (IIASA) as an online tool to compare greenhouse gas (GHG) mitigation proposals by various countries for the year 2020. In this paper, ... Keywords: Business intelligence, Cost curves, Decision model, Interactive system, Optimisation

Thanh Binh Nguyen; Lena Hoeglund-Isaksson; Fabian Wagner; Wolfgang Schoepp

2013-04-01T23:59:59.000Z

100

Tunnel closure calculations  

SciTech Connect

When a deeply penetrating munition explodes above the roof of a tunnel, the amount of rubble that falls inside the tunnel is primarily a function of three parameters: first the cube-root scaled distance from the center of the explosive to the roof of the tunnel. Second the material properties of the rock around the tunnel, and in particular the shear strength of that rock, its RQD (Rock Quality Designator), and the extent and orientation of joints. And third the ratio of the tunnel diameter to the standoff distance (distance between the center of explosive and the tunnel roof). The authors have used CALE, a well-established 2-D hydrodynamic computer code, to calculate the amount of rubble that falls inside a tunnel as a function of standoff distance for two different tunnel diameters. In particular they calculated three of the tunnel collapse experiments conducted in an iron ore mine near Kirkeness, Norway in the summer of 1994. The failure model that they used in their calculations combines an equivalent plastic strain criterion with a maximum tensile strength criterion and can be calibrated for different rocks using cratering data as well as laboratory experiments. These calculations are intended to test and improve the understanding of both the Norway Experiments and the ACE (Array of conventional Explosive) phenomenology.

Moran, B.; Attia, A.

1995-07-01T23:59:59.000Z

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


101

NEUTRON SOURCES  

DOE Patents (OSTI)

A neutron source is obtained without employing any separate beryllia receptacle, as was formerly required. The new method is safer and faster, and affords a source with both improved yield and symmetry of neutron emission. A Be container is used to hold and react with Pu. This container has a thin isolating layer that does not obstruct the desired Pu--Be reaction and obviates procedures previously employed to disassemble and remove a beryllia receptacle. (AEC)

Richmond, J.L.; Wells, C.E.

1963-01-15T23:59:59.000Z

102

Historical river flow rates for dose calculations  

Science Conference Proceedings (OSTI)

Annual average river flow rates are required input to the LADTAP Computer Code for calculating offsite doses from liquid releases of radioactive materials to the Savannah River. The source of information on annual river flow rates used in dose calculations varies, depending on whether calculations are for retrospective releases or prospective releases. Examples of these types of releases are: Retrospective - releases from routine operations (annual environmental reports) and short term release incidents that have occurred. Prospective - releases that might be expected in the future from routine or abnormal operation of existing or new facilities (EIS`s, EID`S, SAR`S, etc.). This memorandum provides historical flow rates at the downstream gauging station at Highway 301 for use in retrospective dose calculations and derives flow rate data for the Beaufort-Jasper and Port Wentworth water treatment plants.

Carlton, W.H.

1991-06-10T23:59:59.000Z

103

Hydrogen Threshold Cost Calculation  

NLE Websites -- All DOE Office Websites (Extended Search)

Program Record (Offices of Fuel Cell Technologies) Program Record (Offices of Fuel Cell Technologies) Record #: 11007 Date: March 25, 2011 Title: Hydrogen Threshold Cost Calculation Originator: Mark Ruth & Fred Joseck Approved by: Sunita Satyapal Date: March 24, 2011 Description: The hydrogen threshold cost is defined as the hydrogen cost in the range of $2.00-$4.00/gge (2007$) which represents the cost at which hydrogen fuel cell electric vehicles (FCEVs) are projected to become competitive on a cost per mile basis with the competing vehicles [gasoline in hybrid-electric vehicles (HEVs)] in 2020. This record documents the methodology and assumptions used to calculate that threshold cost. Principles: The cost threshold analysis is a "top-down" analysis of the cost at which hydrogen would be

104

Steep Slope Calculator  

NLE Websites -- All DOE Office Websites (Extended Search)

Steep Slope Calculator Steep Slope Calculator Estimates Cooling and Heating Savings for Residential Roofs with Non-Black Surfaces Enter A State: Select a state Alabama Alaska Arkansas Arizona California Colorado Connecticut Delaware Florida Georgia Hawaii Iowa Idaho Illinois Indiana Kansas Kentucky Louisiana Maine Maryland Massachusetts Michigan Minnesota Mississippi Missouri Montana North Carolina North Dakota Nebraska Nevada New Hampshire New Jersey New Mexico New York Ohio Oklahoma Oregon Pennsylvania Pacific Islands Puerto Rico Rhode Island South Carolina South Dakota Tennessee Texas Utah Vermont Virginia Washington Wisconsin West Virginia Wyoming Canadian Cities Enter A City: Select a city Click to see Data for All 243 Locations Roof Inputs: R-value(Btu-in/(hr ft2 oF):

105

Information about the Greenhouse Gas Emission Calculations  

NLE Websites -- All DOE Office Websites (Extended Search)

Sources and Assumptions for the Electric and Plug-in Hybrid Vehicle Sources and Assumptions for the Electric and Plug-in Hybrid Vehicle Greenhouse Gas Emissions Calculator To estimate your CO2 emissions rates and generate the bar graph, we used the following sources and assumptions. Your CO2 Emissions Rates Tailpipe (grams CO2/mile) This is the tailpipe CO2 emissions rate for combined city and highway driving that is shown on the fuel economy and environment label for the vehicle model you selected. It is the same regardless of where you live. Total (grams CO2/mile) This includes the vehicle's tailpipe emissions and emissions associated with the production of electricity used to charge the vehicle. For plug-in hybrid electric vehicles, it also includes emissions associated with the production of gasoline. It is estimated using the sources and assumptions below, and will vary based on where you live.

106

Competitive Sourcing  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Competitive Sourcing Competitive Sourcing The Department of Energy's (DOE) Competitive Sourcing program is a management initiative aimed at improving DOE's performance and reducing the Department's operational costs. The program is governed by Office of Management and Budget (OMB) Circular A- 76, Performance of Commercial Activities, dated May 29, 2003. The commercial activities selected for review and competition include functions performed by government employees that are readily available in the private sector, and where the potential for efficiencies, regardless of the winning provider, are highly likely. The candidate functions are chosen from the Department's annual Federal Activities Inventory Reform (FAIR) Act Inventory and subjected to a feasibility review to determine if a prudent business case can be made to enter

107

Neutron source  

DOE Patents (OSTI)

A neutron source which is particularly useful for neutron radiography consists of a vessel containing a moderating media of relatively low moderating ratio, a flux trap including a moderating media of relatively high moderating ratio at the center of the vessel, a shell of depleted uranium dioxide surrounding the moderating media of relatively high moderating ratio, a plurality of guide tubes each containing a movable source of neutrons surrounding the flux trap, a neutron shield surrounding one part of each guide tube, and at least one collimator extending from the flux trap to the exterior of the neutron source. The shell of depleted uranium dioxide has a window provided with depleted uranium dioxide shutters for each collimator. Reflectors are provided above and below the flux trap and on the guide tubes away from the flux trap.

Cason, J.L. Jr.; Shaw, C.B.

1975-10-21T23:59:59.000Z

108

ION SOURCE  

DOE Patents (OSTI)

The ion source described essentially eliminater the problem of deposits of nonconducting materials forming on parts of the ion source by certain corrosive gases. This problem is met by removing both filament and trap from the ion chamber, spacing them apart and outside the chamber end walls, placing a focusing cylinder about the filament tip to form a thin collimated electron stream, aligning the cylinder, slits in the walls, and trap so that the electron stream does not bombard any part in the source, and heating the trap, which is bombarded by electrons, to a temperature hotter than that in the ion chamber, so that the tendency to build up a deposit caused by electron bombardment is offset by the extra heating supplied only to the trap.

Leland, W.T.

1960-01-01T23:59:59.000Z

109

Improved nuclear matter calculations from chiral low-momentum interactions  

Science Conference Proceedings (OSTI)

We present nuclear matter calculations based on low-momentum interactions derived from chiral effective field theory potentials. The current calculations use an improved treatment of the three-nucleon force (3NF) contribution that includes a corrected combinatorial factor beyond Hartree-Fock that was omitted in previous nuclear matter calculations. We find realistic saturation properties using parameters fit only to few-body data, but with larger uncertainty estimates from cutoff dependence and the 3NF parametrization than in previous calculations.

Hebeler, K. [TRIUMF, 4004 Wesbrook Mall, Vancouver, British Columbia, Canada V6T 2A3 (Canada); Department of Physics, Ohio State University, Columbus, Ohio 43210 (United States); Bogner, S. K. [National Superconducting Cyclotron Laboratory and Department of Physics and Astronomy, Michigan State University, East Lansing, Michigan 48844 (United States); Furnstahl, R. J. [Department of Physics, Ohio State University, Columbus, Ohio 43210 (United States); Nogga, A. [Institute for Advanced Simulations, Institut fuer Kernphysik and Juelich Centre for Hadron Physics, Forschungszentrum Juelich, D-52425 Juelich (Germany); Schwenk, A. [ExtreMe Matter Institute EMMI, GSI Helmholtzzentrum fuer Schwerionenforschung GmbH, D-64291 Darmstadt (Germany); Institut fuer Kernphysik, Technische Universitaet Darmstadt, D-64289 Darmstadt (Germany)

2011-03-15T23:59:59.000Z

110

RADIATION SOURCES  

DOE Patents (OSTI)

A novel long-lived source of gamma radiation especially suitable for calibration purposes is described. The source of gamma radiation is denoted mock iodine131, which comprises a naixture of barium-133 and cesium-137. The barium and cesium are present in a barium-cesium ratio of approximately 5.7/1 to 14/1, uniformly dispersed in an ion exchange resin and a filter surrounding the resin comprised of a material of atomic number below approximately 51, and substantially 0.7 to 0.9 millimeter thick.

Brucer, M.H.

1958-04-15T23:59:59.000Z

111

NEUTRON SOURCE  

DOE Patents (OSTI)

A neutron source of the antimony--beryllium type is presented. The source is comprised of a solid mass of beryllium having a cylindrical recess extending therein and a cylinder containing antimony-124 slidably disposed within the cylindrical recess. The antimony cylinder is encased in aluminum. A berylliunn plug is removably inserted in the open end of the cylindrical recess to completely enclose the antimony cylinder in bsryllium. The plug and antimony cylinder are each provided with a stud on their upper ends to facilitate handling remotely.

Reardon, W.A.; Lennox, D.H.; Nobles, R.G.

1959-01-13T23:59:59.000Z

112

Parallel Fission Bank Algorithms in Monte Carlo Criticality Calculations  

E-Print Network (OSTI)

In this work we describe a new method for parallelizing the source iterations in a Monte Carlo criticality calculation. Instead of having one global fission bank that needs to be synchronized, as is traditionally done, our ...

Romano, Paul Kollath

113

PRIMARY SHIELDING CALCULATIONS ON THE IBM 650 (ROC CODES)  

SciTech Connect

Four programs written for the IBM 650 to calculate the gamma dose rates in the primary shielding of thermal reactors are described. Their functions are outlined as follows: Program 651-calculates the core attenuation coefficient and equivalent core gamma volumetric source values for a specific core. Program 652- calculates the activation gamma source data in the shield and prepares tabular data in machine storage for Programs 653 and 654. Program 653- calculates the gamma dose rates in the shield due to gammas arising from activation of shield materials. Program 654calculates the gamma dose rates in the shield due to gammas arising in the core. Gamma photo source values are obtained on the basis of two group neutron flux distributions throughout the reactor core and shield. (W.D.M.)

Rosen, S.S.; Oby, P.V.; Caton, R.L.

1958-10-15T23:59:59.000Z

114

COMPETITIVE SOURCING  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

COMPETITIVE SOURCING COMPETITIVE SOURCING EXECUTIVE STEERING GROUP MEETING PROCEEDINGS June 17, 2002 8:30 am - 11:00 am Room 5E-069 ATTENDEES John Gordon Robert Card Bruce Carnes Kathy Peery Brendan Danaher, AFGE Tony Lane Karen Evans Bill Sylvester Claudia Cross Brian Costlow Laurie Smith Helen Sherman Frank Bessera Rosalie Jordan Dennis O'Brien Mark Hively Robin Mudd Steven Apicella AGENDA 8:30 a.m. - 8:35 a.m. Opening Remarks 8:35a.m. - 8:55 a.m. Executive Steering Group roles and responsibilities, A-76 status, and talking points Team Briefings 8:55 a.m. - 9:20 a.m. Information Technology Study 9:20 a.m. - 9:45 a.m. Financial Services Study

115

ION SOURCE  

DOE Patents (OSTI)

An ion source is described and comprises an arc discharge parallel to the direction of and inside of a magnetic field. an accelerating electrode surrounding substantially all of the discharge except for ion exit apertures, and means for establishing an electric field between that electrode and the arc discharge. the electric field being oriented at an acute angle to the magnetic field. Ions are drawn through the exit apertures in the accelrating electrcde in a direction substantially divergent to the direction of the magnetic field and so will travel in a spiral orbit along the magnetic field such that the ions will not strike the source at any point in their orbit within the magnetic field.

Blue, C.W.; Luce, J.S.

1960-07-19T23:59:59.000Z

116

2011 Radioactive Materials Usage Survey for Unmonitored Point Sources  

SciTech Connect

This report provides the results of the 2011 Radioactive Materials Usage Survey for Unmonitored Point Sources (RMUS), which was updated by the Environmental Protection (ENV) Division's Environmental Stewardship (ES) at Los Alamos National Laboratory (LANL). ES classifies LANL emission sources into one of four Tiers, based on the potential effective dose equivalent (PEDE) calculated for each point source. Detailed descriptions of these tiers are provided in Section 3. The usage survey is conducted annually; in odd-numbered years the survey addresses all monitored and unmonitored point sources and in even-numbered years it addresses all Tier III and various selected other sources. This graded approach was designed to ensure that the appropriate emphasis is placed on point sources that have higher potential emissions to the environment. For calendar year (CY) 2011, ES has divided the usage survey into two distinct reports, one covering the monitored point sources (to be completed later this year) and this report covering all unmonitored point sources. This usage survey includes the following release points: (1) all unmonitored sources identified in the 2010 usage survey, (2) any new release points identified through the new project review (NPR) process, and (3) other release points as designated by the Rad-NESHAP Team Leader. Data for all unmonitored point sources at LANL is stored in the survey files at ES. LANL uses this survey data to help demonstrate compliance with Clean Air Act radioactive air emissions regulations (40 CFR 61, Subpart H). The remainder of this introduction provides a brief description of the information contained in each section. Section 2 of this report describes the methods that were employed for gathering usage survey data and for calculating usage, emissions, and dose for these point sources. It also references the appropriate ES procedures for further information. Section 3 describes the RMUS and explains how the survey results are organized. The RMUS Interview Form with the attached RMUS Process Form(s) provides the radioactive materials survey data by technical area (TA) and building number. The survey data for each release point includes information such as: exhaust stack identification number, room number, radioactive material source type (i.e., potential source or future potential source of air emissions), radionuclide, usage (in curies) and usage basis, physical state (gas, liquid, particulate, solid, or custom), release fraction (from Appendix D to 40 CFR 61, Subpart H), and process descriptions. In addition, the interview form also calculates emissions (in curies), lists mrem/Ci factors, calculates PEDEs, and states the location of the critical receptor for that release point. [The critical receptor is the maximum exposed off-site member of the public, specific to each individual facility.] Each of these data fields is described in this section. The Tier classification of release points, which was first introduced with the 1999 usage survey, is also described in detail in this section. Section 4 includes a brief discussion of the dose estimate methodology, and includes a discussion of several release points of particular interest in the CY 2011 usage survey report. It also includes a table of the calculated PEDEs for each release point at its critical receptor. Section 5 describes ES's approach to Quality Assurance (QA) for the usage survey. Satisfactory completion of the survey requires that team members responsible for Rad-NESHAP (National Emissions Standard for Hazardous Air Pollutants) compliance accurately collect and process several types of information, including radioactive materials usage data, process information, and supporting information. They must also perform and document the QA reviews outlined in Section 5.2.6 (Process Verification and Peer Review) of ES-RN, 'Quality Assurance Project Plan for the Rad-NESHAP Compliance Project' to verify that all information is complete and correct.

Sturgeon, Richard W. [Los Alamos National Laboratory

2012-06-27T23:59:59.000Z

117

2011 Radioactive Materials Usage Survey for Unmonitored Point Sources  

SciTech Connect

This report provides the results of the 2011 Radioactive Materials Usage Survey for Unmonitored Point Sources (RMUS), which was updated by the Environmental Protection (ENV) Division's Environmental Stewardship (ES) at Los Alamos National Laboratory (LANL). ES classifies LANL emission sources into one of four Tiers, based on the potential effective dose equivalent (PEDE) calculated for each point source. Detailed descriptions of these tiers are provided in Section 3. The usage survey is conducted annually; in odd-numbered years the survey addresses all monitored and unmonitored point sources and in even-numbered years it addresses all Tier III and various selected other sources. This graded approach was designed to ensure that the appropriate emphasis is placed on point sources that have higher potential emissions to the environment. For calendar year (CY) 2011, ES has divided the usage survey into two distinct reports, one covering the monitored point sources (to be completed later this year) and this report covering all unmonitored point sources. This usage survey includes the following release points: (1) all unmonitored sources identified in the 2010 usage survey, (2) any new release points identified through the new project review (NPR) process, and (3) other release points as designated by the Rad-NESHAP Team Leader. Data for all unmonitored point sources at LANL is stored in the survey files at ES. LANL uses this survey data to help demonstrate compliance with Clean Air Act radioactive air emissions regulations (40 CFR 61, Subpart H). The remainder of this introduction provides a brief description of the information contained in each section. Section 2 of this report describes the methods that were employed for gathering usage survey data and for calculating usage, emissions, and dose for these point sources. It also references the appropriate ES procedures for further information. Section 3 describes the RMUS and explains how the survey results are organized. The RMUS Interview Form with the attached RMUS Process Form(s) provides the radioactive materials survey data by technical area (TA) and building number. The survey data for each release point includes information such as: exhaust stack identification number, room number, radioactive material source type (i.e., potential source or future potential source of air emissions), radionuclide, usage (in curies) and usage basis, physical state (gas, liquid, particulate, solid, or custom), release fraction (from Appendix D to 40 CFR 61, Subpart H), and process descriptions. In addition, the interview form also calculates emissions (in curies), lists mrem/Ci factors, calculates PEDEs, and states the location of the critical receptor for that release point. [The critical receptor is the maximum exposed off-site member of the public, specific to each individual facility.] Each of these data fields is described in this section. The Tier classification of release points, which was first introduced with the 1999 usage survey, is also described in detail in this section. Section 4 includes a brief discussion of the dose estimate methodology, and includes a discussion of several release points of particular interest in the CY 2011 usage survey report. It also includes a table of the calculated PEDEs for each release point at its critical receptor. Section 5 describes ES's approach to Quality Assurance (QA) for the usage survey. Satisfactory completion of the survey requires that team members responsible for Rad-NESHAP (National Emissions Standard for Hazardous Air Pollutants) compliance accurately collect and process several types of information, including radioactive materials usage data, process information, and supporting information. They must also perform and document the QA reviews outlined in Section 5.2.6 (Process Verification and Peer Review) of ES-RN, 'Quality Assurance Project Plan for the Rad-NESHAP Compliance Project' to verify that all information is complete and correct.

Sturgeon, Richard W. [Los Alamos National Laboratory

2012-06-27T23:59:59.000Z

118

Advanced Photon Source  

NLE Websites -- All DOE Office Websites (Extended Search)

Home Home Group Members Accelerator Magnets Insertion Devices Facilities Presentations & Publications Internal Magnetic Devices Group The primary mission of the Magnetic Devices (MD) Group is to design, build, and maintain Insertion Devices (IDs) that are reliable and transparent to the electron beam at the Advanced Photon Source (APS). The majority of IDs at the APS are conventional planar hybrid undulators, but an essential part of the mission is to develop novel IDs, such as short-period superconducting undulators and long-period electromagnetic undulators. The capabilities of APS IDs are matched to users' experimental needs. The mission also includes magnetic tuning of the IDs to ensure their near-ideal performance as x-ray sources and calculations to predict the radiation

119

Pulse superimposition calculational methodology for estimating the subcritcality level of nuclear fuel assemblies.  

Science Conference Proceedings (OSTI)

One of the most reliable experimental methods for measuring the subcriticality level of a nuclear fuel assembly is the Sjoestrand method applied to the reaction rate generated from a pulsed neutron source. This study developed a new analytical methodology simulating the Sjoestrand method, which allows comparing the experimental and analytical reaction rates and the obtained subcriticality levels. In this methodology, the reaction rate is calculated due to a single neutron pulse using MCNP/MCNPX computer code or any other neutron transport code that explicitly simulates the delayed fission neutrons. The calculation simulates a single neutron pulse over a long time period until the delayed neutron contribution to the reaction rate is vanished. The obtained reaction rate is then superimposed to itself, with respect to the time, to simulate the repeated pulse operation until the asymptotic level of the reaction rate, set by the delayed neutrons, is achieved. The superimposition of the pulse to itself was calculated by a simple C computer program. A parallel version of the C program is used due to the large amount of data being processed, e.g. by the Message Passing Interface (MPI). The analytical results of this new calculation methodology have shown an excellent agreement with the experimental data available from the YALINA-Booster facility of Belarus. This methodology can be used to calculate Bell and Glasstone spatial correction factor.

Talamo, A.; Gohar, Y.; Rabiti, C.; Aliberti, G.; Kondev, F.; Smith, D.; Zhong, Z.; Kiyavitskaya, H.; Bournos, V; Fokov, Y.; Routkovskaya, C.; Serafimovich, I. (Nuclear Engineering Division); (INL); (Joint Institute for Power and Nuclear Research-Sosny)

2009-05-01T23:59:59.000Z

120

BTRIC - Tools & Calculators - ORNL  

NLE Websites -- All DOE Office Websites (Extended Search)

Calculators Calculators Attic Radiant Barrier Calculator Low-Slope Roof Calculator for Commercial Buildings (6/05) - estimates annual energy cost savings Moisture Control for Low-Slope Roofing (5/04) - determine if a roof design needs a vapor retarder or if the roofing system can be modified to enhance its tolerance for small leaks Modified Zone Method Roof Savings Calculator (12/12) - for commerical and residential buildings using whole-building energy simulations Solar Reflectance Index (SRI) Calculator (6/06) Steep-Slope Roof Calculator on Residential Buildings (6/05) - estimate annual energy cost savings Whole-Wall R-Value Calculator 2.0 (10/06) ZIP-Code R-Value Recommendation Calculator (1/08) Roofs/Attics Attic Radiant Barrier Fact Sheet (Jan 2011) Cool Roofs Will Revolutionize the Building Industry Fact Sheet

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


121

Diversity employment and recruitment sources  

SciTech Connect

Effective human resources management has been identified as one of four critical success factors in the Department of Energy Strategic Plan. The Plan states relative to this factor: ``The Department seeks greater alignment of resources with agency priorities and increased diversification of the workforce, including gender, ethnicity, age, and skills. This diversification will bring new thinking and perspectives that heretofore have not had a voice in departmental decision-making.`` This Guide has been developed as a key tool to assist Department of Energy management and administrative staff in achieving Goal 2 of this critical success factor, which is to ``Ensure a diverse and talented workforce.`` There are numerous sources from which to recruit minorities, women and persons with disabilities. Applying creativity and proactive effort, using traditional and non-traditional approaches, and reaching out to various professional, academic and social communities will increase the reservoir of qualified candidates from which to make selections. In addition, outreach initiatives will undoubtedly yield further benefits such as a richer cultural understanding and diversity awareness. The resource listings presented in this Guide are offered to encourage active participation in the diversity recruitment process. This Guide contains resource listings by state for organizations in the following categories: (1) African American Recruitment Sources; (2) Asian American/Pacific Islander Recruitment Sources; (3) Hispanic Recruitment Sources; (4) Native American/Alaskan Native Recruitment Sources; (5) Persons with Disabilities Recruitment Sources; and (6) Women Recruitment Sources.

Not Available

1994-08-01T23:59:59.000Z

122

The status of the spallation neutron source ion source  

SciTech Connect

The ion source for the spallation neutron source (SNS) is a radio-frequency, multicusp source designed to deliver 45 mA of H2 to the SNS accelerator with a pulse length of 1 ms and repetition rate of 60 Hz. A total of three ion sources have been fabricated and commissioned at Lawrence Berkeley National Laboratory and subsequently delivered to the SNS at the Oak Ridge National Laboratory. The ion sources are currently being rotated between operation on the SNS accelerator, where they are involved in ongoing efforts to commission the SNS LINAC, and the hot spare stand (HSS), where high-current tests are in progress. Commissioning work involves operating the source in a low duty-factor mode (pulse width {approx}200 ms and repetition rate {approx}5 Hz) for extended periods of time while the high-current tests involve source operation at full duty-factor of 6 percent (1 ms/60 Hz). This report discusses routine performance of the source employed in the commissioning role as well as the initial results o f high-current tests performed on the HSS.

Welton, R.F.; Stockli, M.P.; Murray, S.N.; Keller, R.

2003-09-11T23:59:59.000Z

123

FAST CALCULATION OF THE LOMB-SCARGLE PERIODOGRAM USING GRAPHICS PROCESSING UNITS  

Science Conference Proceedings (OSTI)

I introduce a new code for fast calculation of the Lomb-Scargle periodogram that leverages the computing power of graphics processing units (GPUs). After establishing a background to the newly emergent field of GPU computing, I discuss the code design and narrate key parts of its source. Benchmarking calculations indicate no significant differences in accuracy compared to an equivalent CPU-based code. However, the differences in performance are pronounced; running on a low-end GPU, the code can match eight CPU cores, and on a high-end GPU it is faster by a factor approaching 30. Applications of the code include analysis of long photometric time series obtained by ongoing satellite missions and upcoming ground-based monitoring facilities, and Monte Carlo simulation of periodogram statistical properties.

Townsend, R. H. D., E-mail: townsend@astro.wisc.ed [Department of Astronomy, University of Wisconsin-Madison, Sterling Hall, 475 N. Charter Street, Madison, WI 53706 (United States)

2010-12-15T23:59:59.000Z

124

Heat Deposition in Positron Sources for ILC  

Science Conference Proceedings (OSTI)

In the International Linear Collider (ILC) positron source, multi-GeV electrons or multi-MeV photons impinge on a metal target to produce the needed positrons in the resulting electromagnetic showers. The incoming beam power is hundreds of kilowatts. Various computer programs -- such as FLUKA or MARS -- can calculate how the incoming beam showers in the target and can track the particle showers through the positron source system. Most of the incoming energy ends up as heat in the various positron source elements. This paper presents results from such calculations and their impact on the design of a positron source for the ILC.

Bharadwaj, V.; Pitthan, R.; Sheppard, J.; Vincke, H.; Wang, J.W.; /SLAC

2006-03-15T23:59:59.000Z

125

Development of methodologies for calculating greenhouse gas emissions from electricity generation for the California climate action registry  

SciTech Connect

The California Climate Action Registry, which will begin operation in Fall 2002, is a voluntary registry for California businesses and organizations to record annual greenhouse gas emissions. Reporting of emissions in the Registry by a participant involves documentation of both ''direct'' emissions from sources that are under the entity's control and ''indirect'' emissions controlled by others. Electricity generated by an off-site power source is considered to be an indirect emission and must be included in the entity's report. Published electricity emissions factors for the State of California vary considerably due to differences in whether utility-owned out-of-state generation, non-utility generation, and electricity imports from other states are included. This paper describes the development of three methods for estimating electricity emissions factors for calculating the combined net carbon dioxide emissions from all generating facilities that provide electricity to Californians. We fi nd that use of a statewide average electricity emissions factor could drastically under- or over-estimate an entity's emissions due to the differences in generating resources among the utility service areas and seasonal variations. In addition, differentiating between marginal and average emissions is essential to accurately estimate the carbon dioxide savings from reducing electricity use. Results of this work will be taken into consideration by the Registry when finalizing its guidance for use of electricity emissions factors in calculating an entity's greenhouse gas emissions.

Price, Lynn; Marnay, Chris; Sathaye, Jayant; Murtishaw, Scott; Fisher, Diane; Phadke, Amol; Franco, Guido

2002-04-01T23:59:59.000Z

126

COMPETITIVE SOURCING  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

EXECUTIVE STEERING GROUP Meeting Proceedings October 30, 2002 Room 6E-069, 10:30 - 12:00 Agenda Opening Remarks Bruce Carnes Competitive Sourcing Update Denny O'Brien Team Briefings Team Leads ESG Discussion/Wrap up Bruce Carnes Attendees Bruce Carnes, Acting Chair MaryAnn Shebek Robert Card Prentis Cook Ambassador Brooks Tony Lane Kyle McSlarrow Karen Evans Suzanne Brennan, NTEU Claudia Cross Brian Costlow Helen Sherman Frank Bessera Laurie Morman Denny O'Brien Travis McCrory Bill Pearce Jeff Dowl Mark Hively Steven Apicella Robin Mudd Bruce Carnes chaired the meeting and began with welcoming NTEU to the meeting. In regard to the OMB's Balanced Scorecard, the Department has achieved a Green on progress and we are close to achieving a yellow on status.

127

Building Energy Software Tools Directory: Popolo Utility Load Calculation  

NLE Websites -- All DOE Office Websites (Extended Search)

Popolo Utility Load Calculation Popolo Utility Load Calculation Popolo Utility Load Calculation is a collection of classes for calculating various heat transfer phenomena. The routines have been written from scratch in C#, and present a modern Applications Programming Interface (API) for .NET Framework programmers, allowing wrappers to be written for very high level languages. It contains classes to calculate solid conduction, convective heat transfer near wall surfaces, air ventilation, radiative heat balance of wall surfaces, transmitted solar radiation through a window, and so on. Users should build up these classes to simulate a whole complex building system. A sample source code to build test cases of BESTEST are provided. Since all the source code is distributed under the GNU General Public License, they can be freely

128

The California Climate Action Registry: Development of methodologies for calculating greenhouse gas emissions from electricity generation  

E-Print Network (OSTI)

Energy Data Report; emissions from imports calculated using U.S.source of energy in the Southwest U.S. Thus, imports from

2002-01-01T23:59:59.000Z

129

2050 Calculator | Open Energy Information  

Open Energy Info (EERE)

0 Calculator 0 Calculator Jump to: navigation, search Tool Summary LAUNCH TOOL Name: 2050 Calculator Agency/Company /Organization: United Kingdom Department of Energy and Climate Change (DECC) Sector: Climate, Energy Focus Area: Renewable Energy, Non-renewable Energy, Biomass, Buildings - Commercial, Buildings - Residential, Economic Development, Geothermal, Greenhouse Gas, Multi-model Integration, Multi-sector Impact Evaluation, Solar, Wind Phase: Evaluate Options, Develop Goals, Prepare a Plan Topics: Analysis Tools, Pathways analysis Resource Type: Online calculator User Interface: Spreadsheet, Website Complexity/Ease of Use: Not Available Website: www.gov.uk/2050-pathways-analysis Country: United Kingdom Web Application Link: 2050-calculator-tool.decc.gov.uk/pathways/1111111111111111111111111111

130

Radiation source  

DOE Patents (OSTI)

A device and method for relativistic electron beam heating of a high-density plasma in a small localized region. A relativistic electron beam generator or accelerator produces a high-voltage electron beam which propagates along a vacuum drift tube and is modulated to initiate electron bunching within the beam. The beam is then directed through a low-density gas chamber which provides isolation between the vacuum modulator and the relativistic electron beam target. The relativistic beam is then applied to a high-density target plasma which typically comprises DT, DD, or similar thermonuclear gas at a density of 10.sup.17 to 10.sup.20 electrons per cubic centimeter. The target gas is ionized prior to application of the relativistic electron beam by means of a laser or other preionization source to form a plasma. Utilizing a relativistic electron beam with an individual particle energy exceeding 3 MeV, classical scattering by relativistic electrons passing through isolation foils is negligible. As a result, relativistic streaming instabilities are initiated within the high-density target plasma causing the relativistic electron beam to efficiently deposit its energy into a small localized region of the high-density plasma target.

Thode, Lester E. (Los Alamos, NM)

1981-01-01T23:59:59.000Z

131

EPRI HRA Calculator Version 5.0  

Science Conference Proceedings (OSTI)

HRA Calculator analyzes and calculates human error probabilities in support of probabilistic risk assessments. HRA Calculator takes ...

2013-09-30T23:59:59.000Z

132

HRA Calculator v. 5.0 BETA  

Science Conference Proceedings (OSTI)

HRA Calculator analyzes and calculates human error probabilities in support of probabilistic risk assessments. HRA Calculator takes ...

2013-04-19T23:59:59.000Z

133

Power Line Calculator for Windows[trademark  

SciTech Connect

The Power Line Calculator (PLC) for Windows [trademark], version 1.0, is a program that describes the electrical characteristics of a transmission or distribution system given user-defined input. This input may consist of a combination of operating currents and phases, symmetric components, power factor, and real or reactive power. The program also allows the user to designate whether currents are present on the system neutral or in the ground. The PLC assumes that any value entered by the user remains fixed (e.g., phase current, power factor), and for underdetermined systems, basic default assumptions are incorporated: the power factor is held at or near 1.0, the net phase current is kept at or near zero, and the phase conductor currents are kept balanced. The program operates through a graphical user interface provided by Microsoft[reg sign] Windows [trademark] (version 3.1 or higher required), and the output is available in both tabular and graphic formats.

Silva, J.M. (Enertech Consultants, Campbell, CA (United States))

1992-12-01T23:59:59.000Z

134

Nucleon Form Factor Measurements and Interpretation  

SciTech Connect

The data base for the form factors of the nucleon obtained from elastic ep scattering is discussed, as well as some recent developments in their calculation.

Charles F. Perdrisat

2007-08-22T23:59:59.000Z

135

Tank farm deflagration rates due to various ignition sources  

SciTech Connect

This supporting document evaluates potential ignition sources, documents calculated deflagration rates in flammable gas tanks from these ignition sources, and assesses the efficacy of controls to mitigate or prevent ignition.

Powers, T.B., Westinghouse Hanford

1996-08-29T23:59:59.000Z

136

A Look Inside the Cash Flow Opportunity Calculator: Calculations and  

NLE Websites -- All DOE Office Websites (Extended Search)

A Look Inside the Cash Flow Opportunity Calculator: Calculations A Look Inside the Cash Flow Opportunity Calculator: Calculations and Methodology Secondary menu About us Press room Contact Us Portfolio Manager Login Facility owners and managers Existing buildings Commercial new construction Industrial energy management Small business Service providers Service and product providers Verify applications for ENERGY STAR certification Design commercial buildings Energy efficiency program administrators Commercial and industrial program sponsors Associations State and local governments Federal agencies Tools and resources Training In This Section Campaigns Commercial building design Communications resources Energy management guidance Financial resources Portfolio Manager Products and purchasing Recognition Research and reports Service and product provider (SPP) resources

137

Iterative acceleration methods for Monte Carlo and deterministic criticality calculations  

Science Conference Proceedings (OSTI)

If you have ever given up on a nuclear criticality calculation and terminated it because it took so long to converge, you might find this thesis of interest. The author develops three methods for improving the fission source convergence in nuclear criticality calculations for physical systems with high dominance ratios for which convergence is slow. The Fission Matrix Acceleration Method and the Fission Diffusion Synthetic Acceleration (FDSA) Method are acceleration methods that speed fission source convergence for both Monte Carlo and deterministic methods. The third method is a hybrid Monte Carlo method that also converges for difficult problems where the unaccelerated Monte Carlo method fails. The author tested the feasibility of all three methods in a test bed consisting of idealized problems. He has successfully accelerated fission source convergence in both deterministic and Monte Carlo criticality calculations. By filtering statistical noise, he has incorporated deterministic attributes into the Monte Carlo calculations in order to speed their source convergence. He has used both the fission matrix and a diffusion approximation to perform unbiased accelerations. The Fission Matrix Acceleration method has been implemented in the production code MCNP and successfully applied to a real problem. When the unaccelerated calculations are unable to converge to the correct solution, they cannot be accelerated in an unbiased fashion. A Hybrid Monte Carlo method weds Monte Carlo and a modified diffusion calculation to overcome these deficiencies. The Hybrid method additionally possesses reduced statistical errors.

Urbatsch, T.J.

1995-11-01T23:59:59.000Z

138

Simplified scheme or radioactive plume calculations  

SciTech Connect

A simplified mathematical scheme to estimate external whole-body $gamma$ radiation exposure rates from gaseous radioactive plumes was developed for the Rio Blanco Gas Field Nuclear Stimulation Experiment. The method enables one to calculate swiftly, in the field, downwind exposure rates knowing the meteorological conditions and $gamma$ radiation exposure rates measured by detectors positioned near the plume source. The method is straightforward and easy to use under field conditions without the help of mini-computers. It is applicable to a wide range of radioactive plume situations. It should be noted that the Rio Blanco experiment was detonated on May 17, 1973, and no seep or release of radioactive material occurred. (auth)

Gibson, T.A.; Montan, D.N.

1976-11-21T23:59:59.000Z

139

Invert Effective Thermal Conductivity Calculation  

SciTech Connect

The objective of this calculation is to evaluate the temperature-dependent effective thermal conductivities of a repository-emplaced invert steel set and surrounding ballast material. The scope of this calculation analyzes a ballast-material thermal conductivity range of 0.10 to 0.70 W/m {center_dot} K, a transverse beam spacing range of 0.75 to 1.50 meters, and beam compositions of A 516 carbon steel and plain carbon steel. Results from this calculation are intended to support calculations that identify waste package and repository thermal characteristics for Site Recommendation (SR). This calculation was developed by Waste Package Department (WPD) under Office of Civilian Radioactive Waste Management (OCRWM) procedure AP-3.12Q, Revision 1, ICN 0, Calculations.

M.J. Anderson; H.M. Wade; T.L. Mitchell

2000-03-17T23:59:59.000Z

140

SHORT CIRCUIT CALCULATION (TEMPORARY POWER)  

SciTech Connect

The purpose and objective of this calculation is to determine the momentary and interrupting duty on the breakers, for 69kV temporary power only.

Yuri Shane

1995-07-24T23:59:59.000Z

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


141

Nomogram calculates power plant coal use  

SciTech Connect

The number of tons of coal burned annually by a generating unit can be calculated by the following formula: Q = 43.8 (MW) (HR) (CF/HV)/10/sup 6/ where: Q = Annual usage, million tons MW = Unit capacity, MW HR = Unit heat rate, Btu/kWh CF = Annual unit capacity factor, % HV = Heating value of coal, Btu/lb The nomogram solves this equation and permits annual coal usage to be estimated quickly for various combinations of the other variables. The nomogram also can be used in reverse to determine such things as the annual capacity factor that a certain coal usage could sustain. Example: An 840-MW unit has an average heat rate of 10,000 Btu/kWh and burns coal with a heating value of 8600 Btu/lb. The annual capacity factor is 60%. Calculate the annual coal usage. Solution: (A) Align 840 on MW scale with 8600 on HV scale and mark intersection with CF scale; (B) align this marked point with 10,000 on HR scale and mark intersection with Reference Line; (C) align this point with 60 on CF scale and extend to Q scale. Read answer as approximately 2.6 million tons/year.

McAlister, J.

1984-05-01T23:59:59.000Z

142

Source Selection | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Source Selection Source Selection Source SelectionSource Selection Boards Source Evaluation Board (SEB) Monthly Status Reporting Requirement (pdf) Source Evaluation Board (SEB)...

143

NUCLEAR CALCULATIONS FOR THE PNPF  

SciTech Connect

The reactivity of the Piqua Nuclear Power Facility (PNPF) was calculated at various loadings using a oneregion (with reflector savings), four-group diffusion equation. These calculations were checked with a two-region, four- group FOG calculation. The thermal group constants were obtained with the TEMPEST II-S/sub 4/ procedure, the fast group constants with FORM. The U/sup 238/ resonance integral was adjusted to make the calculations for the critical assembly fit the measurements and the adjusted parameter was used for the PNPF calculations. The minimum critical loading at 360 deg F was calculated to be 20.4 elements, with and excess reactivity of 0.22% (31 cents) for the minimum critical loading of 21 elements. The excess reactivity wss calculated for core loadings of 19, 37, 61, and 85 elements, which result as the outer rings of element positions are filled consecutively. The isothermal temperature coefficient of reactivity was estimated for several core loadings by using the calculated reactivities at 325 deg F and 585 deg F. The values of the coefficient for 21- and 61-element loadings are --4.6 and --4.9 x 10/sup -5/ delta k/ deg F, respectively. The largest coefficient is --5.0 x 10/sup -6/ delta k/ deg F at a loading of 38 elements. The kinetics parameters 1 and BETA /sub eff/ were calculated using the PERT program. The lifetime is 5.23 x 10/sup -5/ seconds at 325 deg F and 5.67 x 10/sup -6/ at 585 deg F. Beta effective ranged from 0.00689 for and 85-element loading at 325 deg F to 0.00728 for a 19-element loading at 585 deg F. A value of 0.0070 was chosen for kinetics calculations. (auth)

Mountford, L.A.; Hume, J.R.

1963-06-24T23:59:59.000Z

144

factors | OpenEI  

Open Energy Info (EERE)

36 36 Varnish cache server Browse Upload data GDR 429 Throttled (bot load) Error 429 Throttled (bot load) Throttled (bot load) Guru Meditation: XID: 2142253836 Varnish cache server factors Dataset Summary Description This dataset is from the report Operational water consumption and withdrawal factors for electricity generating technologies: a review of existing literature (J. Macknick, R. Newmark, G. Heath and K.C. Hallett) and provides estimates of operational water withdrawal and water consumption factors for electricity generating technologies in the United States. Estimates of water factors were collected from published primary literature and were not modified except for unit conversions. Source National Renewable Energy Laboratory Date Released August 28th, 2012 (2 years ago)

145

Alaska Village Electric Load Calculator  

DOE Green Energy (OSTI)

As part of designing a village electric power system, the present and future electric loads must be defined, including both seasonal and daily usage patterns. However, in many cases, detailed electric load information is not readily available. NREL developed the Alaska Village Electric Load Calculator to help estimate the electricity requirements in a village given basic information about the types of facilities located within the community. The purpose of this report is to explain how the load calculator was developed and to provide instructions on its use so that organizations can then use this model to calculate expected electrical energy usage.

Devine, M.; Baring-Gould, E. I.

2004-10-01T23:59:59.000Z

146

" Row: NAICS Codes; Column: Energy Sources...  

U.S. Energy Information Administration (EIA) Indexed Site

","Row" "Code(a)","Subsector and Industry","Source(b)","Fuel Oil","Fuel Oil(c)","Natural Gas(d)","NGL(e)","Coal","and Breeze","Other(f)","Factors" ,,"Total United States" ,"RSE...

147

A science based emission factor for particulate matter emitted from cotton harvesting  

E-Print Network (OSTI)

Poor regional air quality in some states across the US cotton belt has resulted in increased pressure on agricultural sources of particulate matter (PM) from air pollution regulators. Moreover, inaccurate emission factors used in the calculation of annual emissions inventories led to the identification of cotton harvesting as a significant source of PM10 in California and Arizona. As a result, cotton growers in these states are now required to obtain air quality permits and submit management practice plans detailing the actions taken by the producer to reduce fugitive PM emissions from field operations. The objective of this work was to develop accurate PM emission factors for cotton harvesting in terms of total suspended particulate (TSP), PM10, and PM2.5. Two protocols were developed and used to develop PM emission factors from cotton harvesting operations on three farms in Texas during 2006 and 2007. Protocol one utilized TSP concentrations measured downwind of harvesting operations with meteorological data measured onsite in a dispersion model to back-calculate TSP emission flux values. Flux values, determined with the regulatory dispersion models ISCST3 and AERMOD, were converted to emission factors and corrected with results from particle size distribution (PSD) analyses to report emission factors in terms of PM10 and PM2.5. Emission factors were developed for two-row (John Deere 9910) and sixrow (John Deere 9996) cotton pickers with protocol one. The uncertainty associated with the emission factors developed through protocol one resulted in no significant difference between the emission factors for the two machines. Under the second protocol, emission concentrations were measured onboard the six-row cotton picker as the machine harvested cotton. PM10 and PM2.5 emission factors were developed from TSP emission concentration measurements converted to emission rates using the results of PSD analysis. The total TSP, PM10, and PM2.5 emission factors resulting from the source measurement protocol are 1.64 0.37, 0.55 0.12, and 1.58E- 03 4.5E-04 kg/ha, respectively. These emission factors contain the lowest uncertainty and highest level of precision of any cotton harvesting PM emission factors ever developed. Thus, the emission factors developed through the source sampling protocol are recommended for regulatory use.

Wanjura, John David

2008-05-01T23:59:59.000Z

148

Carbon Calculator for Land Use Change from Biofuels Production (CCLUB). Users' manual and technical documentation.  

SciTech Connect

The Carbon Calculator for Land Use Change from Biofuels Production (CCLUB) calculates carbon emissions from land use change (LUC) for four different ethanol production pathways including corn grain ethanol and cellulosic ethanol from corn stover, miscanthus, and switchgrass. This document discusses the version of CCLUB released May 31, 2012 which includes corn, as did the previous CCLUB version, and three cellulosic feedstocks: corn stover, miscanthus, and switchgrass. CCLUB calculations are based upon two data sets: land change areas and above- and below-ground carbon content. Table 1 identifies where these data are stored and used within the CCLUB model, which is built in MS Excel. Land change area data is from Purdue University's Global Trade Analysis Project (GTAP) model, a computable general equilibrium (CGE) economic model. Section 2 describes the GTAP data CCLUB uses and how these data were modified to reflect shrubland transitions. Feedstock- and spatially-explicit below-ground carbon content data for the United States were generated with a surrogate model for CENTURY's soil organic carbon sub-model (Kwon and Hudson 2010) as described in Section 3. CENTURY is a soil organic matter model developed by Parton et al. (1987). The previous CCLUB version used more coarse domestic carbon emission factors. Above-ground non-soil carbon content data for forest ecosystems was sourced from the USDA/NCIAS Carbon Online Estimator (COLE) as explained in Section 4. We discuss emission factors used for calculation of international greenhouse gas (GHG) emissions in Section 5. Temporal issues associated with modeling LUC emissions are the topic of Section 6. Finally, in Section 7 we provide a step-by-step guide to using CCLUB and obtaining results.

Mueller, S; Dunn, JB; Wang, M (Energy Systems); (Univ. of Illinois at Chicago)

2012-06-07T23:59:59.000Z

149

On Rayleigh Optical Depth Calculations  

Science Conference Proceedings (OSTI)

Many different techniques are used for the calculation of Rayleigh optical depth in the atmosphere. In some cases differences among these techniques can be important, especially in the UV region of the spectrum and under clean atmospheric ...

Barry A. Bodhaine; Norman B. Wood; Ellsworth G. Dutton; James R. Slusser

1999-11-01T23:59:59.000Z

150

Conversion Factor  

Gasoline and Diesel Fuel Update (EIA)

Conversion Factor (Btu per cubic foot) Production Marketed... 1,110 1,106 1,105 1,106 1,109 Extraction Loss ......

151

Radiological Source Terms for Tank Farms Safety Analysis  

Science Conference Proceedings (OSTI)

This document provides Unit Liter Dose factors, atmospheric dispersion coefficients, breathing rates and instructions for using and customizing these factors for use in calculating radiological doses for accident analyses in the Hanford Tank Farms.

COWLEY, W.L.

2000-06-27T23:59:59.000Z

152

Agriculture-related radiation dose calculations  

SciTech Connect

Estimates of radiation dose to the public must be made at each stage in the identification and qualification process leading to siting a high-level nuclear waste repository. Specifically considering the ingestion pathway, this paper examines questions of reliability and adequacy of dose calculations in relation to five stages of data availability (geologic province, region, area, location, and mass balance) and three methods of calculation (population, population/food production, and food production driven). Calculations were done using the model PABLM with data for the Permian and Palo Duro Basins and the Deaf Smith County area. Extra effort expended in gathering agricultural data at succeeding environmental characterization levels does not appear justified, since dose estimates do not differ greatly; that effort would be better spent determining usage of food types that contribute most to the total dose; and that consumption rate and the air dispersion factor are critical to assessment of radiation dose via the ingestion pathway. 17 refs., 9 figs., 32 tabs.

Furr, J.M.; Mayberry, J.J.; Waite, D.A.

1987-10-01T23:59:59.000Z

153

Strategy Guideline: Accurate Heating and Cooling Load Calculations  

SciTech Connect

This guide presents the key criteria required to create accurate heating and cooling load calculations and offers examples of the implications when inaccurate adjustments are applied to the HVAC design process. The guide shows, through realistic examples, how various defaults and arbitrary safety factors can lead to significant increases in the load estimate. Emphasis is placed on the risks incurred from inaccurate adjustments or ignoring critical inputs of the load calculation.

Burdick, A.

2011-06-01T23:59:59.000Z

154

Crab Cavity Phase Noise Calculations  

NLE Websites -- All DOE Office Websites (Extended Search)

of whether or not it is reasonable to consider a conventional positron source for a Tesla formatted beam. The critical issue is that of energy deposition in the conversion...

155

Douglas Factors  

Energy.gov (U.S. Department of Energy (DOE))

The Merit Systems Protection Board in its landmark decision, Douglas vs. Veterans Administration, 5 MSPR 280, established criteria that supervisors must consider in determining an appropriate penalty to impose for an act of employee misconduct. These twelve factors are commonly referred to as Douglas Factors and have been incorporated into the Federal Aviation Administration (FAA) Personnel Management System and various FAA Labor Agreements.

156

Passive solar design calculations with the DOE-2 computer program  

DOE Green Energy (OSTI)

The DOE-2 computer program has been modified to improve modeling of passive-solar buildings by the addition of the custom weighting-factor method. The thermal-load and air-temperature calculation procedure in DOE-2 are described. Assumptions inherent in the use of American Society of Heating, Refrigerating, and Air-Conditioning Engineers (ASHRAE) precalculated and the custom weighting factors are discussed. Calculated results from DOE-2 are compared with measured heat-extraction rates and air temperatures for four buildings. These comparisons indicate that DOE-2 can accurately model direct-gain passive buildings and can treat night-ventilative cooling and water walls in an approximate manner.

Kerrisk, J.F.; Moore, J.E.; Schnurr, N.M.; Hunn, B.D.

1980-01-01T23:59:59.000Z

157

AIM: Web-Based, Residential Energy Calculator for Homeowners  

E-Print Network (OSTI)

This paper discusses AIM, or Assess, Improve, Measure. AIM is an energy efficiency calculator for existing residences that has been developed to provide homeowners, realtors and builders with a method to rate the energy efficiency of an existing house using a minimum number of inputs. To accomplish this, AIM uses DOE-2 loads simulations and a simplified systems model. To simplify the use of the calculator, parameters such as window U-factor, roof and wall insulation, which are normally required for simulations in existing homes, are automatically provided using statistical tables. This allows homeowners to use the calculator with information commonly available during a real estate transaction.

Marshall, K.; Moss, M.; Liu, B.; Culp, C.; Haberl, J.; Herbert, C.

2010-08-01T23:59:59.000Z

158

Optimizing Power Factor Correction  

E-Print Network (OSTI)

The optimal investment for power factor correcting capacitors for Kansas Power and Light Company large power contract customers is studied. Since the billing capacity is determined by dividing the real demand by the power factor (the minimum billing capacity is based on 80 percent of the summer peak billing capacity) and the billing capacity is used to determine the number of kilowatt-hours billed at each pricing tier, the power factor affects both the demand and the energy charge. There is almost no information available in the literature concerning recommended power factor corrections for this situation. The general advice commonly given in the past has been that power factor should be corrected to above 0.9 if it is below that value to begin with, but that does not take into account the facts of the situation studied here. Calculations relevant to a commercial consumer of electricity were made for demands of 200, 400, 800, 1,600, 3,200, and 6,400 kW and monthly energy consumption periods of 100, 150, 200, 300, 400, and 500 hours for several capacitor purchase and installation costs. The results are displayed in a series of graphs that enable annual cost savings and payback periods to be readily determined over a range of commonly encountered parameter values. It is found that it is often economically advantageous to correct a power factor to near unity.

Phillips, R. K.; Burmeister, L. C.

1986-06-01T23:59:59.000Z

159

Comparative Calculations of Solubility Equilibria  

Science Conference Proceedings (OSTI)

The uncertainties in calculated solubilities in the Na-F-PO{sub 4}-HPO{sub 4}-OH system. at 25 C for NaOH concentrations up to 5 mol/kg were assessed. These uncertainties were based on an evaluation of the range of values for the Gibbs energies of the solids. Comparative calculations using the Environmental Simulation Program (ESP) and SOLGASMIX indicated that the variation in activity coefficients with NaOH concentration is much greater in the ESP code than in SOLGASMIX. This resulted in ESP calculating a higher solubility in water and a lower solubility in NaOH concentrations above 1 mol/kg: There was a marked discrepancy in the solubilities of the pure components sodium fluoride and trisodium phosphate predicted by ESP and SOLGASMIX. In addition, different solubilities for these components were obtained using different options in ESP. Because of these observations, a Best Practices Guide for ESP will be assembled.

Beahm, E.C.

2000-07-25T23:59:59.000Z

160

Calibrated Neutron Sources  

Science Conference Proceedings (OSTI)

... NIST designed a compliant source. ... needed for new purposes and as old sources decay ... The figure shows a reprentative energy spectrum from such ...

2013-07-30T23:59:59.000Z

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


161

Electrolytes for power sources  

DOE Patents (OSTI)

Electrolytes for power sources, particularly alkaline and acidic power sources, comprising benzene polysulfonic acids and benzene polyphosphonic acids or salts of such acids.

Doddapaneni, Narayan (Albuquerque, NM); Ingersoll, David (Albuquerque, NM)

1995-01-01T23:59:59.000Z

162

Electrolytes for power sources  

DOE Patents (OSTI)

Electrolytes are disclosed for power sources, particularly alkaline and acidic power sources, comprising benzene polysulfonic acids and benzene polyphosphonic acids or salts of such acids. 7 figures.

Doddapaneni, N.; Ingersoll, D.

1995-01-03T23:59:59.000Z

163

Development of methodologies for calculating greenhouse gas emissions from electricity generation for the California climate action registry  

E-Print Network (OSTI)

Energy Data Report; emissions from imports calculated using U.S.source of energy in the Southwest U.S. Thus, imports from

2002-01-01T23:59:59.000Z

164

Variability of EGRET Gamma-Ray Sources  

E-Print Network (OSTI)

The variability of the high-energy gamma ray sources in the Third EGRET catalog is analyzed by a new method. We re-analyze the EGRET data to calculate a likelihood function for the flux of each source in each observation, both for detections and upper limits. These functions can be combined in a uniform manner with a simple model of the flux distribution to characterize the flux variation by a confidence interval for the relative standard deviation of the flux. The main result is a table of these values for almost all the cataloged sources. As expected, the identified pulsars are steady emitters and the blazars are mostly highly variable. The unidentified sources are heterogeneous, with greater variation at higher Galactic latitude. There is an indication that pulsar wind nebulae are associated with variable sources. There is a population of variable sources along the Galactic plane, concentrated in the inner spiral arms.

P. L. Nolan; W. F. Tompkins; I. A. Grenier; P. F. Michelson

2003-07-10T23:59:59.000Z

165

BWR Source Term Generation and Evaluation  

SciTech Connect

This calculation is a revision of a previous calculation (Ref. 7.5) that bears the same title and has the document identifier BBAC00000-01717-0210-00006 REV 01. The purpose of this revision is to remove TBV (to-be-verified) -41 10 associated with the output files of the previous version (Ref. 7.30). The purpose of this and the previous calculation is to generate source terms for a representative boiling water reactor (BWR) spent nuclear fuel (SNF) assembly for the first one million years after the SNF is discharged from the reactors. This calculation includes an examination of several ways to represent BWR assemblies and operating conditions in SAS2H in order to quantify the effects these representations may have on source terms. These source terms provide information characterizing the neutron and gamma spectra in particles per second, the decay heat in watts, and radionuclide inventories in curies. Source terms are generated for a range of burnups and enrichments (see Table 2) that are representative of the waste stream and stainless steel (SS) clad assemblies. During this revision, it was determined that the burnups used for the computer runs of the previous revision were actually about 1.7% less than the stated, or nominal, burnups. See Section 6.6 for a discussion of how to account for this effect before using any source terms from this calculation. The source term due to the activation of corrosion products deposited on the surfaces of the assembly from the coolant is also calculated. The results of this calculation support many areas of the Monitored Geologic Repository (MGR), which include thermal evaluation, radiation dose determination, radiological safety analyses, surface and subsurface facility designs, and total system performance assessment. This includes MGR items classified as Quality Level 1, for example, the Uncanistered Spent Nuclear Fuel Disposal Container (Ref. 7.27, page 7). Therefore, this calculation is subject to the requirements of the Quality Assurance Requirements and Description (Ref. 7.28). The performance of the calculation and development of this document are carried out in accordance with AP-3.124, ''Design Calculation and Analyses'' (Ref. 7.29).

J.C. Ryman

2003-07-31T23:59:59.000Z

166

Linear source approximation in CASMO5  

Science Conference Proceedings (OSTI)

A Linear Source (LS) approximation has been implemented in the two-dimensional Method of Characteristics (MOC) transport solver in a prototype version of CASMO5. The LS approximation, which relies on the computation of trajectory-based spatial moments over source regions to obtain the linear source expansion coefficients, improves the solution accuracy relative to the 'flat' or constant source approximation. In addition, the LS formulation is capable of treating arbitrarily-shaped source regions and is compatible with standard Coarse-Mesh Finite Difference (CMFD) acceleration. Numerical tests presented in this paper for the C5G7 MOX benchmark show that, for comparable accuracy with respect to the reference solution, the LS approximation can reduce the run time by a factor of four and the memory requirements by a factor often relative to the FS scheme. (authors)

Ferrer, R.; Rhodes, J. [Studsvik Scandpower, Inc., 504 Shoup Ave., Idaho Falls, ID 83402 (United States); Smith, K. [Dept. of Nuclear Science and Engineering, Massachusetts Inst. of Technology, 77 Massachusetts Avenue, Cambridge, MA 02139 (United States)

2012-07-01T23:59:59.000Z

167

rf improvements for Spallation Neutron Source H ion source  

Science Conference Proceedings (OSTI)

The Spallation Neutron Source at Oak Ridge National Laboratory is ramping up the accelerated proton beam power to 1.4 MW and just reached 1 MW. The rf-driven multicusp ion source that originates from the Lawrence Berkeley National Laboratory has been delivering 38 mA H beam in the linac at 60 Hz, 0.9 ms. To improve availability, a rf-driven external antenna multicusp ion source with a water-cooled ceramic aluminum nitride AlN plasma chamber is developed. Computer modeling and simulations have been made to analyze and optimize the rf performance of the new ion source. Operational statistics and test runs with up to 56 mA medium energy beam transport beam current identify the 2 MHz rf system as a limiting factor in the system availability and beam production. Plasma ignition system is under development by using a separate 13 MHz system. To improve the availability of the rf power system with easier maintenance, we tested a 70 kV isolation transformer for the 80 kW, 6% duty cycle 2 MHz amplifier to power the ion source from a grounded solid-state amplifier. 2010 American Institute of Physics.

Kang, Yoon W [ORNL; Fuja, Raymond E [ORNL; Goulding, Richard Howell [ORNL; Hardek, Thomas W [ORNL; Lee, Sung-Woo [ORNL; McCarthy, Mike [ORNL; Piller, Chip [ORNL; Shin, Ki [ORNL; Stockli, Martin P [ORNL; Welton, Robert F [ORNL

2010-01-01T23:59:59.000Z

168

Form factors from lattice QCD  

Science Conference Proceedings (OSTI)

Precision computation of hadronic physics with lattice QCD is becoming feasible. The last decade has seen precent-level calculations of many simple properties of mesons, and the last few years have seen calculations of baryon masses, including the nucleon mass, accurate to a few percent. As computational power increases and algorithms advance, the precise calculation of a variety of more demanding hadronic properties will become realistic. With this in mind, I discuss the current lattice QCD calculations of generalized parton distributions with an emphasis on the prospects for well-controlled calculations for these observables as well. I will do this by way of several examples: the pion and nucleon form factors and moments of the nucleon parton and generalized-parton distributions.

Dru Renner

2012-04-01T23:59:59.000Z

169

A COMPARISON OF MEASURED AND CALCULATED GAMMA RAY ATTENUATION FOR A COMMON COUNTING GEOMETRY  

Science Conference Proceedings (OSTI)

In order to perform quantitative gamma spectroscopy, it is necessary to know the sample-specific detection efficiency for photons as a function of energy. The detection efficiency, along with the branching ratio for the isotope and gamma ray of interest, is used to convert observed counts/second to actual disintegrations/second, and, hence, has a large effect on the accuracy of the measurement. In cases where the geometry of the source is simple and reproducible, such as a point source, small vial of solid, or jar of liquid, geometry-specific standards may be counted to determine the detection efficiency. In cases where the samples are large, irregular, or unique, this method generally cannot be used. For example, it is impossible to obtain a NIST-traceable standard glovebox or 55-gallon drum. In these cases, a combination of measured absolute detector efficiency and calculated sample-specific correction factors is commonly used. The correction factors may be calculated via Monte Carlo simulation of the item (the method used by Canberra's ISOCS system), or via semi-empirical calculation of matrix and container attenuations based on the thickness and composition of the container and radioactive matrix (ISOTOPIC by EG&G Ortec uses this method). The accuracy of these correction factors for specific geometries is often of vital interest when assessing the quality of gamma spectroscopy data. During the Building 251 Risk-Reduction Project, over 100 samples of high activity actinides will be characterized via gamma spectroscopy, typically without removing the material from the current storage containers. Most of the radioactive materials in B-251 are stored in cylindrical stainless steel canisters (called USV containers, after the Underground Storage Vaults they are commonly stored in), 13 cm in diameter, by 28 cm high, with walls that are 1.8 mm thick. While the actual samples have a variety of configurations inside the USV container, a very common configuration is the material (usually as an oxide powder pellet of approximately 2 cm diameter by {approx}2 mm thick) in a squat glass jar, with the jar placed in a thin steel food-pack can, which is then placed in the bottom of the USV canister. During data acquisition, the USV containers are typically rotated at approximately 4 rpm on a turntable to eliminate errors due to the material not being centered in the can, or attenuation not being isotropic. An aluminum plate is placed over the container, secured by three vertical rods, to securely hold the container. Pictures of both the containers, and this typical counting configuration are shown below.

Gaylord, R F

2004-02-26T23:59:59.000Z

170

An overview of LINAC ion sources  

SciTech Connect

This paper discusses ion sources used in high-duty-factor proton and H{sup -} Linacs as well as in accelerators utilizing multi-charged heavy ions, mostly for nuclear physics applications. The included types are Electron Cyclotron Resonance (ECR) sources as well as filament and rf driven multicusp sources. The paper does not strive to attain encyclopedic character but rather to highlight major lines of development, peak performance parameters and type-specific limitations and problems of these sources. The main technical aspects being discussed are particle feed, plasma generation and ion production by discharges, and plasma confinement.

Keller, Roderich [Los Alamos National Laboratory

2008-01-01T23:59:59.000Z

171

H- radio frequency source development at the Spallation Neutron Source  

Science Conference Proceedings (OSTI)

The Spallation Neutron Source (SNS) now routinely operates nearly 1 MW of beam power on target with a highly persistent {approx}38 mA peak current in the linac and an availability of {approx}90%. H{sup -} beam pulses ({approx}1 ms, 60 Hz) are produced by a Cs-enhanced, multicusp ion source closely coupled with an electrostatic low energy beam transport (LEBT), which focuses the 65 kV beam into a radio frequency quadrupole accelerator. The source plasma is generated by RF excitation (2 MHz, {approx}60 kW) of a copper antenna that has been encased with a thickness of {approx}0.7 mm of porcelain enamel and immersed into the plasma chamber. The ion source and LEBT normally have a combined availability of {approx}99%. Recent increases in duty-factor and RF power have made antenna failures a leading cause of downtime. This report first identifies the physical mechanism of antenna failure from a statistical inspection of {approx}75 antennas which ran at the SNS, scanning electron microscopy studies of antenna surface, and cross sectional cuts and analysis of calorimetric heating measurements. Failure mitigation efforts are then described which include modifying the antenna geometry and our acceptance/installation criteria. Progress and status of the development of the SNS external antenna source, a long-term solution to the internal antenna problem, are then discussed. Currently, this source is capable of delivering comparable beam currents to the baseline source to the SNS and, an earlier version, has briefly demonstrated unanalyzed currents up to {approx}100 mA (1 ms, 60 Hz) on the test stand. In particular, this paper discusses plasma ignition (dc and RF plasma guns), antenna reliability, magnet overheating, and insufficient beam persistence.

Welton, Robert F [ORNL; Pennisi, Terry R [ORNL; Roseberry, Ron T [ORNL; Stockli, Martin P [ORNL

2012-01-01T23:59:59.000Z

172

AGING FACILITY CRITICALITY SAFETY CALCULATIONS  

Science Conference Proceedings (OSTI)

The purpose of this design calculation is to revise and update the previous criticality calculation for the Aging Facility (documented in BSC 2004a). This design calculation will also demonstrate and ensure that the storage and aging operations to be performed in the Aging Facility meet the criticality safety design criteria in the ''Project Design Criteria Document'' (Doraswamy 2004, Section 4.9.2.2), and the functional nuclear criticality safety requirement described in the ''SNF Aging System Description Document'' (BSC [Bechtel SAIC Company] 2004f, p. 3-12). The scope of this design calculation covers the systems and processes for aging commercial spent nuclear fuel (SNF) and staging Department of Energy (DOE) SNF/High-Level Waste (HLW) prior to its placement in the final waste package (WP) (BSC 2004f, p. 1-1). Aging commercial SNF is a thermal management strategy, while staging DOE SNF/HLW will make loading of WPs more efficient (note that aging DOE SNF/HLW is not needed since these wastes are not expected to exceed the thermal limits form emplacement) (BSC 2004f, p. 1-2). The description of the changes in this revised document is as follows: (1) Include DOE SNF/HLW in addition to commercial SNF per the current ''SNF Aging System Description Document'' (BSC 2004f). (2) Update the evaluation of Category 1 and 2 event sequences for the Aging Facility as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2004c, Section 7). (3) Further evaluate the design and criticality controls required for a storage/aging cask, referred to as MGR Site-specific Cask (MSC), to accommodate commercial fuel outside the content specification in the Certificate of Compliance for the existing NRC-certified storage casks. In addition, evaluate the design required for the MSC that will accommodate DOE SNF/HLW. This design calculation will achieve the objective of providing the criticality safety results to support the preliminary design of the Aging Facility. As the ongoing design evolution remains fluid, the results from this design calculation should be evaluated for applicability to any new or modified design. Consequently, the results presented in this document are limited to the current design. The information contained in this document was developed by Environmental and Nuclear Engineering and is intended for the use of Design and Engineering in its work regarding the various criticality related activities performed in the Aging Facility. Yucca Mountain Project personnel from Environmental and Nuclear Engineering should be consulted before the use of the information for purposes other than those stated herein or use by individuals other than authorized personnel in Design and Engineering.

C.E. Sanders

2004-09-10T23:59:59.000Z

173

Source Selection Guide | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Source Selection Guide Source Selection Guide Source Selection Guide More Documents & Publications Source Selection Guide Source Selection Guide Source Selection...

174

Nonnegative matrix factorization with quadratic programming  

Science Conference Proceedings (OSTI)

Nonnegative matrix factorization (NMF) solves the following problem: find such nonnegative matrices A@?R"+^I^x^J and X@?R"+^J^x^K that Y@?AX, given only Y@?R^I^x^K and the assigned index J (K@?I>=J). Basically, the factorization is achieved by alternating ... Keywords: Blind source separation, Nonnegative matrix factorization, Quadratic programming

Rafal Zdunek; Andrzej Cichocki

2008-06-01T23:59:59.000Z

175

Variational learning for rectified factor analysis  

Science Conference Proceedings (OSTI)

Linear factor models with non-negativity constraints have received a great deal of interest in a number of problem domains. In existing approaches, positivity has often been associated with sparsity. In this paper we argue that sparsity of the factors ... Keywords: Positive factor analysis, Source separation, Variational Bayes

Markus Harva; Ata Kabn

2007-03-01T23:59:59.000Z

176

Review of Axial Burnup Distribution Considerations for Burnup Credit Calculations  

SciTech Connect

This report attempts to summarize and consolidate the existing knowledge on axial burnup distribution issues that are important to burnup credit criticality safety calculations. Recently released Nuclear Regulatory Commission (NRC) staff guidance permits limited burnup credit, and thus, has prompted resolution of the axial burnup distribution issue. The reactivity difference between the neutron multiplication factor (keff) calculated with explicit representation of the axial burnup distribution and keff calculated assuming a uniform axial burnup is referred to as the ``end effect.'' This end effect is shown to be dependent on many factors, including the axial-burnup profile, total accumulated burnup, cooling time, initial enrichment, assembly design, and the isotopics considered (i.e., actinide-only or actinides plus fission products). Axial modeling studies, efforts related to the development of axial-profile databases, and the determination of bounding axial profiles are also discussed. Finally, areas that could benefit from further efforts are identified.

Wagner, J.C.; DeHart, M.D.

2000-03-01T23:59:59.000Z

177

Light Source Notes | Advanced Photon Source  

NLE Websites -- All DOE Office Websites (Extended Search)

of the Linear Lattice of the APS Storage Ring Vadim Sajaev,Louis Emery LS-292 Direct-Drive and Eddy-Current Septum Magnets Suk Hong Kim LS-291 Calculation of Pulsed Kicker...

178

An approximate algorithm for the flux from a rectangular volume source  

SciTech Connect

An exact semi-analytic formula for the flux from a rectangular surface source with a slab shield has been derived and the required function table has been calculated. This formula is the basis for an algorithm which gives a good approximation for the flux from a rectangular volume source. No other hand calculation method for this source geometry is available in the literature.

Wallace, O.J.

1994-11-09T23:59:59.000Z

179

Limits of heralded single photon sources based on parametric photon pair generation  

E-Print Network (OSTI)

We derive calculations on the statistics of a heralded single photon source based on parametric photon pair generation. These calculations highlight fundamental and practical limits for these sources, and show which physical parameters can be optimized to improve the quality of a real source.

Virally, Stphane; Godbout, Nicolas

2009-01-01T23:59:59.000Z

180

Limits of heralded single photon sources based on parametric photon pair generation  

E-Print Network (OSTI)

We derive calculations on the statistics of a heralded single photon source based on parametric photon pair generation. These calculations highlight fundamental and practical limits for these sources, and show which physical parameters can be optimized to improve the quality of a real source.

Stphane Virally; Suzanne Lacroix; Nicolas Godbout

2009-10-13T23:59:59.000Z

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


181

Source Tree Composition  

E-Print Network (OSTI)

Dividing software systems in components improves software reusability as well as software maintainability. Components live at several levels, we concentrate on the implementation level where components are formed by source files, divided over directory structures. Such source code components are usually strongly coupled in the directory structure of a software system. Their compilation is usually controlled by a single global build process. This entangling of source trees and build processes often makes reuse of source code components in different software systems difficult. It also makes software systems inflexible because integration of additional source code components in source trees and build processes is difficult. This paper's subject is to increase software reuse by decreasing coupling of source code components. It is achieved by automized assembly of software systems from reusable source code components and involves integration of source trees, build processes, and configuration processes. Application domains include generative programming, product-line architectures, and commercial off-the-shelf (COTS) software engineering.

Merijn De Jonge

2001-01-01T23:59:59.000Z

182

Energy Savings Calculator for Commercial Boilers: Closed Loop, Space  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Savings Calculator for Commercial Boilers: Closed Loop, Savings Calculator for Commercial Boilers: Closed Loop, Space Heating Applications Only Energy Savings Calculator for Commercial Boilers: Closed Loop, Space Heating Applications Only October 8, 2013 - 2:23pm Addthis This cost calculator is a screening tool that estimates a product's lifetime energy cost savings at various efficiency levels. Learn more about the base model and other assumptions. Project Type Is this a new installation or a replacement? New Replacement What is the deliverable fluid type? Water Steam What fuel is used? Gas Oil How many boilers will you purchase? unit(s) Performance Factors Existing What is the capacity of the existing boiler? MBtu/hr* What is the thermal efficiency of the existing boiler? % Et New What is the capacity of the new boiler?

183

Excited State Effects in Nucleon Matrix Element Calculations  

SciTech Connect

We perform a high-statistics precision calculation of nucleon matrix elements using an open sink method allowing us to explore a wide range of sink-source time separations. In this way the influence of excited states of nucleon matrix elements can be studied. As particular examples we present results for the nucleon axial charge g{sub A} and for the first moment of the isovector unpolarized parton distribution x{sub u-d}. In addition, we report on preliminary results using the generalized eigenvalue method for nucleon matrix elements. All calculations are performed using N{sub f} = 2+1+1 maximally twisted mass Wilson fermions.

Constantia Alexandrou, Martha Constantinou, Simon Dinter, Vincent Drach, Karl Jansen, Theodoros Leontiou, Dru B Renner

2011-12-01T23:59:59.000Z

184

NERSC Calculations Provide Independent Confirmation of Global...  

NLE Websites -- All DOE Office Websites (Extended Search)

NERSC Calculations Provide Independent Confirmation of Global Land Warming Since 1901 NERSC Calculations Provide Independent Confirmation of Global Land Warming Since 1901...

185

Federal Energy Management Program: Energy Savings Calculator...  

NLE Websites -- All DOE Office Websites (Extended Search)

Savings Calculator for Commercial Boilers (Closed Loop, Space Heating Applications Only) This cost calculator is a screening tool that estimates a product's lifetime energy cost...

186

Hybrid Car Calculator | Open Energy Information  

Open Energy Info (EERE)

Hybrid Car Calculator Jump to: navigation, search Tool Summary Name: Hybrid Car Calculator AgencyCompany Organization: New American Dream Phase: "Evaluate Options and Determine...

187

Weigel, Southworth, and Meyer 1 Calculators for Estimating Greenhouse Gas Emissions from Public  

E-Print Network (OSTI)

electricity emissions, inventory calculators utilize data from the U.S. EPA's eGRID database of electrical power generation emission factors (32). The eGRID emission factors include neither upstream fuel power generation emission factors (lbs GHGs/MWh) from the EPA's eGRID database (32). Regional electric

188

Energy Calculator- Common Units and Conversions  

NLE Websites -- All DOE Office Websites (Extended Search)

Energy Calculator - Common Units and Conversions Energy Calculator - Common Units and Conversions Calculators for Energy Used in the United States: Coal Electricity Natural Gas Crude Oil Gasoline Diesel & Heating Oil Coal Conversion Calculator Short Tons Btu Megajoules Metric Tons Clear Calculate 1 Short Ton = 20,169,000 Btu (based on U.S. consumption, 2007) Electricity Conversion Calculator KilowattHours Btu Megajoules million Calories Clear Calculate 1 KilowattHour = 3,412 Btu Natural Gas Conversion Calculator Cubic Feet Btu Megajoules Cubic Meters Clear Calculate 1 Cubic Foot = 1,028 Btu (based on U.S. consumption, 2007); 1 therm = 100,000 Btu; 1 terajoule = 1,000,000 megajoules Crude Oil Conversion Calculator Barrels Btu Megajoules Metric Tons* Clear Calculate 1 Barrel = 42 U.S. gallons = 5,800,000 Btu (based on U.S. consumption,

189

Next Generation Light Source  

Next Generation Light Source Super Thin Light Bulb, Energy Efficient, Long Life, Dimmable, and Uniform Illumination High Entry Barrier 71 ...

190

Sources of Thermodynamic Data  

Science Conference Proceedings (OSTI)

...The thermodynamic data summarized in Table 2 are collected from a variety of sources. The certainty with which

191

Atmospheric Longwave Irradiance Uncertainty: Pyrgeometers Compared to an Absolute Sky-Scanning Radiometer, Atmospheric Emitted Radiance Interferometer, and Radiative Transfer Model Calculations  

SciTech Connect

Because atmospheric longwave radiation is one of the most fundamental elements of an expected climate change, there has been a strong interest in improving measurements and model calculations in recent years. Important questions are how reliable and consistent are atmospheric longwave radiation measurements and calculations and what are the uncertainties? The First International Pyrgeometer and Absolute Sky-scanning Radiometer Comparison, which was held at the Atmospheric Radiation Measurement program's Souther Great Plains site in Oklahoma, answers these questions at least for midlatitude summer conditions and reflects the state of the art for atmospheric longwave radiation measurements and calculations. The 15 participating pyrgeometers were all calibration-traced standard instruments chosen from a broad international community. Two new chopped pyrgeometers also took part in the comparison. And absolute sky-scanning radiometer (ASR), which includes a pyroelectric detector and a reference blackbody source, was used for the first time as a reference standard instrument to field calibrate pyrgeometers during clear-sky nighttime measurements. Owner-provided and uniformly determined blackbody calibration factors were compared. Remarkable improvements and higher pyrgeometer precision were achieved with field calibration factors. Results of nighttime and daytime pyrgeometer precision and absolute uncertainty are presented for eight consecutive days of measurements, during which period downward longwave irradiance varied between 260 and 420 W m-2. Comparisons between pyrgeometers and the absolute ASR, the atmospheric emitted radiance interferometer, and radiative transfer models LBLRTM and MODTRAN show a surprisingly good agreement of <2 W m-2 for nighttime atmospheric longwave irradiance measurements and calculations.

Philipona, J. R.; Dutton, Ellsworth G.; Stoffel, T.; Michalsky, Joseph J.; Reda, I.; Stifter, Armin; Wendling, Peter; Wood, Norm; Clough, Shepard A.; Mlawer, Eli J.; Anderson, Gail; Revercomb, Henry E.; Shippert, Timothy R.

2001-06-04T23:59:59.000Z

192

Approach for Calculating OE Benefits  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Reliability Reliability U.S. Department of Energy - 1000 Independence Ave., SW Washington, DC 20585 2007 Electricity Delivery and Energy Reliability Joe Paladino October 29, 2007 Approach for Calculating OE Benefits Challenges * Established benefits methodologies (e.g., NEMS and MARKAL) do not address some of the major benefits that OE's program will provide (e.g. reliability). * Much of OE's program is about transforming the way the T&D infrastructure operates rather than replacing components: - Some technologies need a high penetration or must be deployed as an entire system to yield benefits (e.g. PMUs or Distribution Automation). - Some programs within OE are not developing "widgets" that can be easily counted. - OE is developing tools/methodologies or funding demonstrations that

193

Shielding calculations at dismantled synchrocyclotron  

SciTech Connect

The Space Radiation Effects Laboratory located in Newport News, Virginia, was operated by the College of William and Mary for the National Aeronautics and Space Administration. A synchrocyclotron which was formerly in operation in this building was removed in 1980. At several locations, the scattered radiation caused an induced radioactivity within the walls of the cyclotron room. A radiological survey has been performed to determine the amount of residual radioactivity on the walls. Calculations were performed to determine the thickness of the concrete walls and floor for shielding the residual radiation in the cyclotron room. Recommendations are made to minimize exposures from the residual radioactivity on the walls and floor of the cyclotron room to potential occupants working in the building. 19 refs., 1 fig., 2 tabs.

Yalcintas, M.G.

1987-01-01T23:59:59.000Z

194

Interruption Cost Estimate Calculator | Open Energy Information  

Open Energy Info (EERE)

Interruption Cost Estimate Calculator Interruption Cost Estimate Calculator Jump to: navigation, search Tool Summary Name: Interruption Cost Estimate (ICE) Calculator Agency/Company /Organization: Freeman, Sullivan & Co. Sector: Energy Focus Area: Grid Assessment and Integration, Energy Efficiency Resource Type: Online calculator, Software/modeling tools User Interface: Website Website: icecalculator.com/ Country: United States Cost: Free Northern America References: [1] Logo: Interruption Cost Estimate (ICE) Calculator This calculator is a tool designed for electric reliability planners at utilities, government organizations or other entities that are interested in estimating interruption costs and/or the benefits associated with reliability improvements. About The Interruption Cost Estimate (ICE) Calculator is an electric reliability

195

DC source assemblies  

SciTech Connect

Embodiments of DC source assemblies of power inverter systems of the type suitable for deployment in a vehicle having an electrically grounded chassis are provided. An embodiment of a DC source assembly comprises a housing, a DC source disposed within the housing, a first terminal, and a second terminal. The DC source also comprises a first capacitor having a first electrode electrically coupled to the housing, and a second electrode electrically coupled to the first terminal. The DC source assembly further comprises a second capacitor having a first electrode electrically coupled to the housing, and a second electrode electrically coupled to the second terminal.

Campbell, Jeremy B; Newson, Steve

2013-02-26T23:59:59.000Z

196

Alternative Fuels Data Center: Vehicle Cost Calculator  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Vehicle Cost Vehicle Cost Calculator to someone by E-mail Share Alternative Fuels Data Center: Vehicle Cost Calculator on Facebook Tweet about Alternative Fuels Data Center: Vehicle Cost Calculator on Twitter Bookmark Alternative Fuels Data Center: Vehicle Cost Calculator on Google Bookmark Alternative Fuels Data Center: Vehicle Cost Calculator on Delicious Rank Alternative Fuels Data Center: Vehicle Cost Calculator on Digg Find More places to share Alternative Fuels Data Center: Vehicle Cost Calculator on AddThis.com... Vehicle Cost Calculator Vehicle Cost Calculator This tool uses basic information about your driving habits to calculate total cost of ownership and emissions for makes and models of most vehicles, including alternative fuel and advanced technology vehicles. Also

197

Energy Input Output Calculator | Open Energy Information  

Open Energy Info (EERE)

Input Output Calculator Input Output Calculator Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Energy Input-Output Calculator Agency/Company /Organization: Department of Energy Sector: Energy Focus Area: Energy Efficiency Resource Type: Online calculator User Interface: Website Website: www2.eere.energy.gov/analysis/iocalc/Default.aspx Web Application Link: www2.eere.energy.gov/analysis/iocalc/Default.aspx OpenEI Keyword(s): Energy Efficiency and Renewable Energy (EERE) Tools Language: English References: EERE Energy Input-Output Calculator[1] The Energy Input-Output Calculator (IO Calculator) allows users to estimate the economic development impacts from investments in alternate electricity generating technologies. About the Calculator The Energy Input-Output Calculator (IO Calculator) allows users to estimate

198

Analysis Of Factors Affecting Natural Source Slf Electromagnetic...  

Open Energy Info (EERE)

sensor orientation and the received artificial electromagnetic interference, influence of weather conditions on the data quality and so on. The results showed that (1) There is an...

199

Ion Sources - Cyclotron  

NLE Websites -- All DOE Office Websites (Extended Search)

Sources Sources The 88-Inch Cyclotron is fed by three Electron Cyclotron Resonance (ECR) high-charge-state ion sources, the ECR, the AECR, and VENUS, currently the most powerful ECR ion source in the world. Built to answer the demand for intense heavy ion beams, these high performance ion sources enable the 88-Inch Cyclotron to accelerate beams of ions from hydrogen to uranium. The ECR ion sources allow the efficient use of rare isotopes of stable elements, either from natural or enriched sources. A variety of metallic ion beams are routinely produced in our low temperature oven (up to 600°C) and our high temperature oven (up to 2100°C). Furthermore, the ability to produce "cocktails" (mixtures of beams) for the Berkeley Accelerator Space Effects (BASE) Facility adds tremendously to the flexibility of the 88-Inch Cyclotron.

200

HRA Calculator, Version 4.21 DEMO  

Science Conference Proceedings (OSTI)

HRA Calculator analyzes and calculates human error probabilities in support of probabilistic risk assessments. HRA Calculator takes a toolbox approach that uses a variety of HRA methods. The PRA Tools / HRA Calculator User Group was formed in 2000 to address the industrys need for HRA tools and to encourage consistency in HRA results. Version 4.21 adds value by expanding the HRA Calculator methods applied, overcoming past limitations on particular parameters, improving the ...

2013-03-07T23:59:59.000Z

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


201

HRA Calculator Version 4.2  

Science Conference Proceedings (OSTI)

HRA Calculator analyzes and calculates human error probabilities in support of probabilistic risk assessments. HRA Calculator takes a 8220toolboxapproach that uses a variety of HRA methods. The PRA Tools / HRA Calculator User Group was formed in 2000 to address the industryneed for HRA tools and to encourage consistency in HRA results. Version 4.2 adds value by expanding the HRA Calculator methods applied, overcoming past limitations on particular parameters, improving the dependency analysis features, ...

2010-11-19T23:59:59.000Z

202

ILC Electron Source Injector Simuations  

SciTech Connect

As part of the global project aimed at proposing an efficient design for the ILC (International Linear Collider), we simulated possible setups for the electron source injector, which will provide insight into how the electron injector for the ILC should be designed in order to efficiently accelerate the electron beams through the bunching system. This study uses three types of software: E-Gun to simulate electron beam emission, Superfish to calculate solenoidal magnetic fields, and GPT (General Particle Tracer) to trace charged particles after emission through magnetic fields and subharmonic bunchers. We performed simulations of the electron source injector using various electron gun bias voltages (140kV - 200kV), emitted beam lengths (500ps - 1ns) and radii (7mm - 10mm), and electromagnetic field strengths of the first subharmonic buncher (5 - 20 MV/m). The results of the simulations show that for the current setup of the ILC, a modest electron gun bias voltage ({approx}140kV) is sufficient to achieve the required bunching of the beam in the injector. Extensive simulations of parameters also involving the second subharmonic buncher should be performed in order to gain more insight into possible efficient designs for the ILC electron source injector.

Lakshmanan, Manu; /Cornell U., LNS /SLAC

2007-08-29T23:59:59.000Z

203

Carbon-14 Background, Pathway, and Dose Calculation Analysis for Nuclear Power Plants: A Sourcebook for Accurate Carbon-14 Dose Calculations  

Science Conference Proceedings (OSTI)

Commercial nuclear power plants (NPPs) generate carbon-14 during operation, and release it in power plant effluents. This report explores the current state of carbon and carbon-14 science and understanding to identify and recommend any enhancements to carbon-14 dose calculation methodologies.BackgroundWhile the amount of carbon-14 released by NPPs is small compared to natural and other anthropogenic sources, it is important to accurately document it, along ...

2013-12-11T23:59:59.000Z

204

Ultra-Bright Source Of Polarization-Entangled Photons  

NLE Websites -- All DOE Office Websites (Extended Search)

Ultra-Bright Source Of Polarization-Entangled Photons Ultra-Bright Source Of Polarization-Entangled Photons Ultra-Bright Source Of Polarization-Entangled Photons Utilizing the process of spontaneous parametric down-conversion in a novel crystal geometry, a source of polarization-entangled photon pairs has been provided that is more than ten times brighter, per unit of pump power, than previous sources, with another factor of 30 to 75 expected to be readily achievable. Available for thumbnail of Feynman Center (505) 665-9090 Email Ultra-Bright Source Of Polarization-Entangled Photons Utilizing the process of spontaneous parametric down-conversion in a novel crystal geometry, a source of polarization-entangled photon pairs has been provided that is more than ten times brighter, per unit of pump power, than previous sources, with another factor of 30 to 75 expected to be readily

205

A New Source Biasing Approach in ADVANTG  

Science Conference Proceedings (OSTI)

The ADVANTG code has been developed at Oak Ridge National Laboratory to generate biased sources and weight window maps for MCNP using the CADIS and FW-CADIS methods. In preparation for an upcoming RSICC release, a new approach for generating a biased source has been developed. This improvement streamlines user input and improves reliability. Previous versions of ADVANTG generated the biased source from ADVANTG input, writing an entirely new general fixed-source definition (SDEF). Because volumetric sources were translated into SDEF-format as a finite set of points, the user had to perform a convergence study to determine whether the number of source points used accurately represented the source region. Further, the large number of points that must be written in SDEF-format made the MCNP input and output files excessively long and difficult to debug. ADVANTG now reads SDEF-format distributions and generates corresponding source biasing cards, eliminating the need for a convergence study. Many problems of interest use complicated source regions that are defined using cell rejection. In cell rejection, the source distribution in space is defined using an arbitrarily complex cell and a simple bounding region. Source positions are sampled within the bounding region but accepted only if they fall within the cell; otherwise, the position is resampled entirely. When biasing in space is applied to sources that use rejection sampling, current versions of MCNP do not account for the rejection in setting the source weight of histories, resulting in an 'unfair game'. This problem was circumvented in previous versions of ADVANTG by translating volumetric sources into a finite set of points, which does not alter the mean history weight ({bar w}). To use biasing parameters without otherwise modifying the original cell-rejection SDEF-format source, ADVANTG users now apply a correction factor for {bar w} in post-processing. A stratified-random sampling approach in ADVANTG is under development to automatically report the correction factor with estimated uncertainty. This study demonstrates the use of ADVANTG's new source biasing method, including the application of {bar w}.

Bevill, Aaron M [ORNL; Mosher, Scott W [ORNL

2012-01-01T23:59:59.000Z

206

The new beamline 3 at SURF III for source-based radiometry  

Science Conference Proceedings (OSTI)

... Blackbody radiation is calculable by the temperature of the cavity and the ... 5 However, the spectral distribution of a black- body source depends ...

2010-08-18T23:59:59.000Z

207

ILC Positron source simualtion  

NLE Websites -- All DOE Office Websites (Extended Search)

capture studies: how well does this work? Essentially want zero field on target Energy deposition calculations for RAL material optimization: start with 5-D acceptance...

208

Spallation Neutron Source, SNS  

NLE Websites -- All DOE Office Websites (Extended Search)

Spallation Neutron Source Spallation Neutron Source Providing the most intense pulsed neutron beams in the world... Accumulator Ring Commissioning Latest Step for Spallation Neutron Source The Spallation Neutron Source, located at Oak Ridge National Laboratory, has passed another milestone on the way to completion this year--the commissioning of the proton accumulator ring. Brookhaven led the design and construction of the accumulator ring, which will allow an order of magnitude more beam power than any other facility in the world. The Spallation Neutron Source (SNS) is an accelerator-based neutron source being built in Oak Ridge, Tennessee, by the U.S. Department of Energy. The figure on the right shows a schematic of the accumulator ring and transport beam lines that are being designed and built by Brookhaven

209

Dynamic radioactive particle source  

SciTech Connect

A method and apparatus for providing a timed, synchronized dynamic alpha or beta particle source for testing the response of continuous air monitors (CAMs) for airborne alpha or beta emitters is provided. The method includes providing a radioactive source; placing the radioactive source inside the detection volume of a CAM; and introducing an alpha or beta-emitting isotope while the CAM is in a normal functioning mode.

Moore, Murray E.; Gauss, Adam Benjamin; Justus, Alan Lawrence

2012-06-26T23:59:59.000Z

210

Load Balancing Of Parallel Monte Carlo Transport Calculations  

National Nuclear Security Administration (NNSA)

Load Balancing Of Parallel Load Balancing Of Parallel Monte Carlo Transport Calculations R.J. Procassini, M. J. O'Brien and J.M. Taylor Lawrence Livermore National Laboratory, P. O. Box 808, Livermore, CA 94551 The performance of parallel Monte Carlo transport calculations which use both spatial and particle parallelism is increased by dynamically assigning processors to the most worked domains. Since the particle work load varies over the course of the simulation, each cycle this algorithm determines if dynamic load balancing would speed up the calculation. If load balancing is required, a small number of particle communications are initiated in order to achieve load balance. This method has decreased the parallel run time by more than a factor of three for certain criticality

211

Locating Sources of Data  

Science Conference Proceedings (OSTI)

Table 4   Guides and directories to sources of materials data and information...1993 The CD-ROM Directory 1993, TFPL Publishing, Washington, DC, 1993.

212

AnthroSources  

Science Conference Proceedings (OSTI)

... placed into the HANIM format (www.hanim.org) and existing animation sequences are applied. The original source of the animations comes from ...

213

Sources of Corrosion Information  

Science Conference Proceedings (OSTI)

Table 3   Sources of corrosion information...Sci.chem.electrochem Newsgroup www.groups.google.com/groups?group=sci.chem..electrochem/...

214

Brochures | Advanced Photon Source  

NLE Websites -- All DOE Office Websites (Extended Search)

Podcasts Image Gallery external site Video Library Syndicated Feeds (RSS) The Advanced Photon Source: Lighting the Way to a Better Tomorrow aps brochure The APS helps...

215

Publications | Advanced Photon Source  

NLE Websites -- All DOE Office Websites (Extended Search)

compendium of information on results from research at the APS. It is the official source for listing APS-related journal articles, conference proceedings and papers,...

216

Divisions | Advanced Photon Source  

NLE Websites -- All DOE Office Websites (Extended Search)

Chart Argonne Research Divisions APS Research Divisions In May 2002, The Advanced Photon Source was reorganized into three divisions: the Accelerator Systems Division...

217

Improved ion source  

DOE Patents (OSTI)

A magnetic filter for an ion source reduces the production of undesired ion species and improves the ion beam quality. High-energy ionizing electrons are confined by the magnetic filter to an ion source region, where the high-energy electrons ionize gas molecules. One embodiment of the magnetic filter uses permanent magnets oriented to establish a magnetic field transverse to the direction of travel of ions from the ion source region to the ion extraction region. In another embodiment, low energy 16 eV electrons are injected into the ion source to dissociate gas molecules and undesired ion species into desired ion species,

Leung, K.N.; Ehlers, K.W.

1982-05-04T23:59:59.000Z

218

Electromagnetic form factors of hadrons  

SciTech Connect

A vector meson dominance model of the electromagnetic form factors of hadrons is developed which is based on the use of unstable particle propagators. Least-square fits are made to the proton, neutron, pion and kaon form factor data in both the space and time-like regions. A good fit to the low-energy nucleon form factor data is obtained using only rho, $omega$, and phi dominance, and leads to a determination of the vector meson resonance parameters in good agreement with experiment. The nucleon-vector meson coupling constants obey simple sum rules indicating that there exists no hard core contribution to the form factors within theoretical uncertainties. The prediction for the electromagnetic radii of the proton is in reasonable agreement with recent experiments. The pion and kaon charge form factors as deduced from the nucleon form factors assuming vector meson universality are compared to the data. The pion form factor agrees with the data in both the space and time-like regions. The pion charge radius is in agreement with the recent Dubna result, but the isovector P-wave pion-pion phase shift calculated from the theory disagrees with experiment. A possible contribution to the form factors from a heavy rho meson is also evaluated. (auth)

Zidell, V.S.

1976-01-01T23:59:59.000Z

219

Improvements in transport calculations by the optimized multigroup libraries for fast neutron systems  

SciTech Connect

This paper shows how to improve the accuracy of the transport calculations using in the APOLLO2 code the optimized multigroup libraries calculated by AEMC for fast neutron systems. These ameliorations concern the fission source calculation and the self-shielding models. The calculation of the fission source was generalized to fission spectra including an incident neutron energy dependence. The subgroup self-shielding model was updated for a mixture of resonant nuclides. Some tests on a Pu-239 sphere without reflectors and a fast sodium cell show that the use of four fission spectra guarantees a correct representation of the fission source. The test on a Pu-239 sphere with a thick steel reflector proves that the subgroup self-shielding, accounting for the mutual shielding of several resonant nuclides, allows us to improve the accuracy of the neutron transport solution in the reflector. (authors)

Mosca, P.; Mounier, C.; Bellier, P.; Zmijarevic, I. [Commissariat a l'Energie Atomique et Aux Energies Alternatives (CEA-Saclay), 91191 Gif-sur Yvette Cedex (France)

2012-07-01T23:59:59.000Z

220

Building Energy Software Tools Directory: Duct Calculator  

NLE Websites -- All DOE Office Websites (Extended Search)

Duct Calculator Duct Calculator Duct Calculator logo. Provides access to duct calculation and sizing capabilities either as a standalone Windows program or from within the Autodesk Building Mechanical, the new HVAC-oriented version of AutoCAD. Based on the engineering data and procedures outlined in the ASHRAE Fundamentals Handbook Calculation Methods, Duct Calculator features an advanced and fully interactive user interface. Slide controls for air flow, velocity, friction and duct size provide real-time, interactive feedback; as you spin one, the others dynamically respond in real time. When used with Autodesk Building Mechanical, Duct Calculator streamlines the design process by automatically re-sizing whole branches of ductwork. Screen Shots Keywords duct-sizing, design, engineering, calculation

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


221

Vehicle Cost Calculator | Open Energy Information  

Open Energy Info (EERE)

Vehicle Cost Calculator Vehicle Cost Calculator Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Vehicle Cost Calculator Agency/Company /Organization: National Renewable Energy Laboratory Sector: Energy Focus Area: Transportation Phase: Evaluate Options Resource Type: Online calculator User Interface: Website Website: www.afdc.energy.gov/calc/ Web Application Link: www.afdc.energy.gov/calc/ OpenEI Keyword(s): Energy Efficiency and Renewable Energy (EERE) Tools Language: English References: Vehicle Cost Calculator[1] Logo: Vehicle Cost Calculator Calculate the total cost of ownership and emissions for makes and models of most vehicles, including alternative fuel and advanced technology vehicles. Overview This tool uses basic information about your driving habits to calculate

222

Systematic Tendency Error in Budget Calculations  

Science Conference Proceedings (OSTI)

Atmospheric budget calculations suffer from various observational and numerical errors. This paper demonstrates that all budget calculations applied to a large number of samples suffer from additional errors originating from systematic tendency ...

Masao Kanamitsu; Suranjana Saha

1996-06-01T23:59:59.000Z

223

SPC/E Water Reference Calculations  

Science Conference Proceedings (OSTI)

SPC/E Water Reference Calculations - Ewald Summation. In ... 5. Sample Configurations of SPC/E Water Molecules. Four ...

2013-09-16T23:59:59.000Z

224

Fusion reactors as future energy sources  

SciTech Connect

From conference on energy policies and the international system; New, Delhi, India (4 Dec 1973). The need is now apparent for a global energy policy with the following characteristics: Compatibility with environmental and economic factors; large fuel resources, the recovery and exploration of which have minimal environmental impact and which do not introduce disturbing factors into the world political situation. Fusion power in this context is discussed, including assessments of its potential and of the problems yet to be solved in achieving its realization. The proposition is advanced that fusion should be considered as the ultimate source of energy, and that other sources of energy, including conventional nuclear power, should be considered as interim sources. (auth)

Post, R.F.; Ribe, F.L.

1973-01-01T23:59:59.000Z

225

Radiation Source Replacement Workshop  

Science Conference Proceedings (OSTI)

This report summarizes a Radiation Source Replacement Workshop in Houston Texas on October 27-28, 2010, which provided a forum for industry and researchers to exchange information and to discuss the issues relating to replacement of AmBe, and potentially other isotope sources used in well logging.

Griffin, Jeffrey W.; Moran, Traci L.; Bond, Leonard J.

2010-12-01T23:59:59.000Z

226

PORTABLE SOURCE OF RADIOACTIVITY  

DOE Patents (OSTI)

A portable source for radiogiaphy or radiotherapy is described. It consists of a Tl/sup 170/ or Co/sup 60/ source mounted in a rotatable tungsten alloy plug. The plug rotates within a brass body to positions of safety or exposure. Provision is made for reloading and carrying the device safely. (T.R.H.)

Goertz, R.C.; Ferguson, K.R.; Rylander, E.W.; Safranski, L.M.

1959-06-16T23:59:59.000Z

227

Chemical Plume Source Localization  

Science Conference Proceedings (OSTI)

This paper addresses the problem of estimating a likelihood map for the location of the source of a chemical plume using an autonomous vehicle as a sensor probe in a fluid flow. The fluid flow is assumed to have a high Reynolds number. Therefore, the ... Keywords: Autonomous vehicles, Bayesian inference methods, chemical plume tracing, online mapping, online planning, plume source localization

Shuo Pang; J. A. Farrell

2006-10-01T23:59:59.000Z

228

Status Report of NNLO QCD Calculations  

Science Conference Proceedings (OSTI)

We review recent progress in next-to-next-to-leading order (NNLO) perturbative QCD calculations with special emphasis on results ready for phenomenological applications. Important examples are new results on structure functions and jet or Higgs boson production. In addition, we describe new calculational techniques based on twistors and their potential for efficient calculations of multiparticle amplitudes.

Klasen, Michael [Institute for Nuclear Theory, University of Washington, Box 351550, Seattle, WA 98195-1550 (United States)

2005-10-06T23:59:59.000Z

229

source | OpenEI  

Open Energy Info (EERE)

source source Dataset Summary Description This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report (AEO2011). This dataset is table 17, and contains only the reference case. The dataset uses quadrillion Btu. The data is broken down into marketed renewable energy, residential, commercial, industrial, transportation and electric power. Source EIA Date Released April 26th, 2011 (3 years ago) Date Updated Unknown Keywords Commercial Electric Power Industrial Renewable Energy Consumption Residential sector source transportation Data application/vnd.ms-excel icon AEO2011: Renewable Energy Consumption by Sector and Source- Reference Case (xls, 105 KiB) Quality Metrics Level of Review Peer Reviewed Comment

230

Photonic crystal light source  

DOE Patents (OSTI)

A light source is provided by a photonic crystal having an enhanced photonic density-of-states over a band of frequencies and wherein at least one of the dielectric materials of the photonic crystal has a complex dielectric constant, thereby producing enhanced light emission at the band of frequencies when the photonic crystal is heated. The dielectric material can be a metal, such as tungsten. The spectral properties of the light source can be easily tuned by modification of the photonic crystal structure and materials. The photonic crystal light source can be heated electrically or other heating means. The light source can further include additional photonic crystals that exhibit enhanced light emission at a different band of frequencies to provide for color mixing. The photonic crystal light source may have applications in optical telecommunications, information displays, energy conversion, sensors, and other optical applications.

Fleming, James G. (Albuquerque, NM); Lin, Shawn-Yu (Albuquerque, NM); Bur, James A. (Corrales, NM)

2004-07-27T23:59:59.000Z

231

Neutron sources and applications  

Science Conference Proceedings (OSTI)

Review of Neutron Sources and Applications was held at Oak Brook, Illinois, during September 8--10, 1992. This review involved some 70 national and international experts in different areas of neutron research, sources, and applications. Separate working groups were asked to (1) review the current status of advanced research reactors and spallation sources; and (2) provide an update on scientific, technological, and medical applications, including neutron scattering research in a number of disciplines, isotope production, materials irradiation, and other important uses of neutron sources such as materials analysis and fundamental neutron physics. This report summarizes the findings and conclusions of the different working groups involved in the review, and contains some of the best current expertise on neutron sources and applications.

Price, D.L. [ed.] [Argonne National Lab., IL (United States); Rush, J.J. [ed.] [National Inst. of Standards and Technology, Gaithersburg, MD (United States)

1994-01-01T23:59:59.000Z

232

The calculation of satellite line structures in highly stripped plasmas  

SciTech Connect

This is the final report of a three-year, Laboratory Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). Recently developed high-resolution x-ray spectrographs have made it possible to measure satellite structures from various plasma sources with great detail. These lines are weak optically thin lines caused by the decay of dielectronic states and generally accompany the resonance lines of H-like and He-like ions. The Los Alamos atomic physics and kinetics codes provide a unique capability for calculating the position and intensities of such lines. These programs have been used to interpret such highly resolved spectral measurements from pulsed power devices and laser produced plasmas. Some of these experiments were performed at the LANL Bright Source and Trident laser facilities. The satellite structures are compared with calculations to diagnose temperatures and densities. The effect of non-thermal electron distributions of electrons on calculated spectra was also considered. Collaborations with Russian scientists have added tremendous value to this research die to their vast experience in x-ray spectroscopy.

Abdallah, J. Jr.; Kilcrease, D.P. [Los Alamos National Lab., NM (United States); Faenov, A.Ya.; Pikuz, T.A. [Multicharged Ion Spectra Data Center, Moscow (Russian Federation)

1998-11-01T23:59:59.000Z

233

Calculation of free-energy differences and potentials of mean force by a multi-energy gap method  

E-Print Network (OSTI)

Calculation of free-energy differences and potentials of mean force by a multi-energy gap method the convergence of free-energy calculations. It introduces a bias factor in Monte Carlo simulations or.e., the difference in energy function between two states, and is therefore specifically designed for calculating free-energy

Weston, Ken

234

Distributed Energy Calculator | Open Energy Information  

Open Energy Info (EERE)

Distributed Energy Calculator Distributed Energy Calculator Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Distributed Energy Calculator Agency/Company /Organization: Apps for Energy Challenge Participant Sector: Energy Resource Type: Application prototype User Interface: Website Website: distributedenergycalculator.com/ OpenEI Keyword(s): Challenge Generated, Green Button Apps Language: English References: Apps for Energy[1] The Distributed Energy Calculator allows you to explore the potential energy savings for your community using Solar, Small Wind or Microturbines. The Distributed Energy Calculator allows you to explore the potential energy savings for your community using Solar, Small Wind or Microturbines. You can upload Green Button Data to compare your utility energy costs to

235

Chalmers Climate Calculator | Open Energy Information  

Open Energy Info (EERE)

Chalmers Climate Calculator Chalmers Climate Calculator Jump to: navigation, search Tool Summary Name: Chalmers Climate Calculator Agency/Company /Organization: Chalmers University of Technology Sector: Energy, Land Topics: Baseline projection, Co-benefits assessment, GHG inventory, Pathways analysis Resource Type: Software/modeling tools User Interface: Website Website: dhcp2-pc011134.fy.chalmers.se Cost: Free Chalmers Climate Calculator Screenshot References: Chalmers Climate Calculator[1] Logo: Chalmers Climate Calculator " In the Chalmers Climate Calculator the user can decide on when and how fast emissions of CO2 are reduced and what this emissions scenario implies in terms of CO2 concentration and global average surface temperature change. The climate sensitivity and the net aerosol forcing in year 2005

236

Harmonic Analysis Errors in Calculating Dipole,  

NLE Websites -- All DOE Office Websites (Extended Search)

Harmonic Analysis Errors in Calculating Dipole, Harmonic Analysis Errors in Calculating Dipole, Quadrupole, and Sextupole Magnets using POISSON Ro be rt J. La ri<::::R~ i. September 10, 1985 Introduction LS-32 The computer program POISSON was used to calculate the dipole, quadru- pole, and sextupole magnets of the 6 GeV electron storage ring. A trinagular mesh must first be generated by LATTICE. The triangle size is varied over the "universe" at the discretion of the user. This note describes a series of test calculations that were made to help the user decide on the size of the mesh to reduce the harmonic field calculation errors. A conformal transfor- mation of a multipole magnet into a dipole reduces these errors. Dipole Magnet Calculations A triangular mesh used to calculate a "perfect" dipole magnet is shown in

237

Unidentified gamma-ray sources off the Galactic plane as low-mass microquasars?  

E-Print Network (OSTI)

A subset of the unidentified EGRET gamma-ray sources with no active galactic nucleus or other conspicuous counterpart appears to be concentrated at medium latitudes. Their long-term variability and their spatial distribution indicate that they are distinct from the more persistent sources associated with the nearby Gould Belt. They exhibit a large scale height of 1.3 +/- 0.6 kpc above the Galactic plane. Potential counterparts for these sources include microquasars accreting from a low-mass star and spewing a continuous jet. Detailed calculations have been performed of the jet inverse Compton emission in the radiation fields from the star, the accretion disc, and a hot corona. Different jet Lorentz factors, powers, and aspect angles have been explored. The up-scattered emission from the corona predominates below 100 MeV whereas the disc and stellar contributions are preponderant at higher energies for moderate (~15 deg) and small (~1 deg) aspect angles, respectively. Yet, unlike in the high-mass, brighter versions of these systems, the external Compton emission largely fails to produce the luminosities required for 5 to 10 kpc distant EGRET sources. Synchrotron-self-Compton emission appears as a promising alternative.

I. A. Grenier; M. M. Kaufman Bernado; G. E. Romero

2004-08-12T23:59:59.000Z

238

Shielding Design of the Spallation Neutron Source (SNS)  

Science Conference Proceedings (OSTI)

The shielding design is important for the construction of an intense high-energy accelerator facility like the proposed Spallation Neutron Source (SNS) due to its impact on conventional facility design, maintenance operations, and since the cost for the radiation shielding shares a considerable part of the total facility costs. A calculational strategy utilizing coupled high energy Monte Carlo calculations and multi-dimensional discrete ordinates calculations, along with semi-empirical calculations, was implemented to perform the conceptual design shielding assessment of the proposed SNS. Biological shields have been designed and assessed for the proton beam transport system and associated beam dumps, the target station, and the target service cell and general remote maintenance cell. Shielding requirements have been assessed with respect to weight, space, and dose-rate constraints for operating, shutdown, and accident conditions. A discussion of the proposed facility design, conceptual design shielding requirements, calculational strategy, source terms, preliminary results and conclusions, and recommendations for additional analyses are presented.

Johnson, J.O.

1998-09-17T23:59:59.000Z

239

The Spallation Neutron Source (SNS) conceptual design shielding analysis  

SciTech Connect

The shielding design is important for the construction of an intense high-energy accelerator facility like the proposed Spallation Neutron Source (SNS) due to its impact on conventional facility design, maintenance operations, and since the cost for the radiation shielding shares a considerable part of the total facility costs. A calculational strategy utilizing coupled high energy Monte Carlo calculations and multi-dimensional discrete ordinates calculations, along with semi-empirical calculations, was implemented to perform the conceptual design shielding assessment of the proposed SNS. Biological shields have been designed and assessed for the proton beam transport system and associated beam dumps, the target station, and the target service cell and general remote maintenance cell. Shielding requirements have been assessed with respect to weight, space, and dose-rate constraints for operating, shutdown, and accident conditions. A discussion of the proposed facility design, conceptual design shielding requirements calculational strategy, source terms, preliminary results and conclusions, and recommendations for additional analyses are presented.

Johnson, J.O.; Odano, N.; Lillie, R.A.

1998-03-01T23:59:59.000Z

240

Microfabricated diffusion source  

DOE Patents (OSTI)

A microfabricated diffusion source to provide for a controlled diffusion rate of a vapor comprises a porous reservoir formed in a substrate that can be filled with a liquid, a headspace cavity for evaporation of the vapor therein, a diffusion channel to provide a controlled diffusion of the vapor, and an outlet to release the vapor into a gas stream. The microfabricated diffusion source can provide a calibration standard for a microanalytical system. The microanalytical system with an integral diffusion source can be fabricated with microelectromechanical systems technologies.

Oborny, Michael C. (Albuquerque, NM); Frye-Mason, Gregory C. (Cedar Crest, NM); Manginell, Ronald P. (Albuquerque, NM)

2008-07-15T23:59:59.000Z

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


241

Development and application of the spatially explicit load enrichment calculation tool (select) to determine potential E. coli loads in watersheds  

E-Print Network (OSTI)

According to the USEPA National Section 303(d) List Fact Sheet, bacterial pathogens are the leading cause of water quality impairments in Texas. The automated Spatially Explicit Load Enrichment Calculation Tool (SELECT) uses spatially variable factors such as land use, soil condition, and distance to streams to characterize pathogen sources across a watershed. The results support development of Total Maximum Daily Loads (TMDLs) where bacterial contamination is of concern. SELECT calculates potential E. coli loads by distributing the contributing source populations across suitable habitats, applying a fecal production rate, and then aggregating the potential load to the subwatersheds. SELECT provides a Graphical User Interface (GUI), developed in Visual Basic for Applications (VBA) within ArcGIS 9.X, where project parameters can be adjusted for various pollutant loading scenarios. A new approach for characterizing E. coli loads resulting from on-site wastewater treatment systems (OWTSs) was incorporated into the SELECT methodology. The pollutant connectivity factor (PCF) module was created to identify areas potentially contributing E. coli loads to waterbodies during runoff events by weighting the influence of potential loading, runoff potential, and travel distance. Simulation results indicate livestock and wildlife are potentially contributing large amounts of E. coli in the Lake Granbury Watershed in areas where these contributing sources are not currently monitored for E. coli. The bacterial water quality violations near Lake Granbury are most likely the result of malfunctioning OWTSs and pet waste in the runoff. The automated SELECT was verified by characterizing the potential E. coli loading in the Plum Creek Watershed and comparing to results from a prior study (Teague, 2007). The E. coli potential load for the watershed was lower than the previous study due to major differences in assumptions. Comparing the average ranked PCF estimated by physical properties of the watershed with the statistical clustering of watershed characteristics provided similar groupings. SELECT supports the need to evaluate each contributing source separately to effectively allocate site specific best management practices (BMPs). This approach can be used as a screening step for determining areas where detailed investigation is merited. SELECT in conjunction with PCF and clustering analysis can assist decision makers develop Watershed Protection Plans (WPPs) and determine TMDLs.

Riebschleager, Kendra Jean

2008-08-01T23:59:59.000Z

242

National Synchrotron Light Source  

NLE Websites -- All DOE Office Websites (Extended Search)

Environmental Assessment Environmental Assessment Proposed Upgrade and Improvement of the National Synchrotron Light Source Complex at Brookhaven National Laboratory, Upton, New York This Environmental Assessment addresses the proposed action by the U.S. Department of Energy to upgrade the facilities of the National Synchrotron Light Source Complex, namely the National Synchrotron Light Source (NSLS), the Accelerator Test Facility and the Source Development Laboratory. The environmental effects of a No-Action Alternative as well as a Proposed Action are evaluated in the Environmental Assessment. The “NSLS Environmental Assessment Fact Sheet” link below leads to a one-page summary of the Environmental Assessment. The “NSLS Environmental Assessment” link below leads to the whole 41-page

243

Alternative fuel information sources  

DOE Green Energy (OSTI)

This short document contains a list of more than 200 US sources of information (Name, address, phone number, and sometimes contact) related to the use of alternative fuels in automobiles and trucks. Electric-powered cars are also included.

Not Available

1994-06-01T23:59:59.000Z

244

Sources of Error  

Science Conference Proceedings (OSTI)

...Sources of error in damage tolerance analysis can be classified as: Uncertainty and assumptions in data input Uncertainty due to assumptions about flaws Interpretations of, and assumptions in, stress history Inaccuracies in stress intensity Computer...

245

Source Remediation vs. Plume  

E-Print Network (OSTI)

This summary paper reviews just some of the extensive scientific literature from the past 20 years on the various aspects of contaminant source remediation and plume management. Some of the major findings of the numerous research projects are presented.

Management Critical Factors; G. Teutsch; H. Rgner; D. Zamfirescu; M. Finkel; M. Bittens

2001-01-01T23:59:59.000Z

246

About | Advanced Photon Source  

NLE Websites -- All DOE Office Websites (Extended Search)

the APS Welcome to the Advanced Photon Source Here you will find an introduction and tour of the facility, as well as information about the organizations and opportunities at...

247

Specific Sources of Data  

Science Conference Proceedings (OSTI)

Table 5   Sources of materials data...ASM International, 1989, 1224 pp (C) NIST High Temperature Superconductors Database, Ceramics Division, National Institute of Standards and Technology, Gaithersburg,

248

Atmospheric Dispersion from Elevated Sources in an Urban Area: Comparison between Tracer Experiments and Model Calculations  

Science Conference Proceedings (OSTI)

Atmospheric dispersion experiments were carried out in the Copenhagen area under neutral and unstable conditions. The tracer sulphurhexafluoride was released without buoyancy from a tower at a height of 115 m and then collected at ground-level ...

Sven-Erik Gryning; Erik Lyck

1984-04-01T23:59:59.000Z

249

CALCULATION OF PULSED KICKER MAGNETIC FIELD ATTENUATION INSIDE BEAM CHAMBERS  

NLE Websites -- All DOE Office Websites (Extended Search)

CALCULATION OF PULSED KICKER MAGNETIC FIELD ATTENUATION CALCULATION OF PULSED KICKER MAGNETIC FIELD ATTENUATION INSIDE BEAM CHAMBERS S. H. Kim January 8, 2001 1. Introduction and Summary The ceramic beam chambers in the sections of the kicker magnets for the beam injection and extraction in the Advanced Photon Source (APS) are made of alumina. The inner surface of the ceramic chamber is coated with a conductive paste. The choice of coating thickness is intended to reduce the shielding of the pulsed kicker magnetic field while containing the electromagnetic fields due to the beam bunches inside the chamber, and minimize the Ohmic heating due to the fields on the chamber [1]. The thin coating generally does not give a uniform surface resistivity for typical dimensions of the ceramic chambers in use. The chamber cross section is a circular or

250

Spallation Neutron Source  

NLE Websites -- All DOE Office Websites (Extended Search)

D/gim D/gim Spallation Neutron Source SNS is an accelerator-based neutron source. This one-of-a-kind facility pro- vides the most intense pulsed neutron beams in the world. When ramped up to its full beam power of 1.4 MW, SNS will be eight times more powerful than today's best facility. It will give researchers more detailed snapshots of the smallest samples of physical and biological materials than ever before

251

Field emission electron source  

DOE Patents (OSTI)

A novel field emitter material, field emission electron source, and commercially feasible fabrication method is described. The inventive field emission electron source produces reliable electron currents of up to 400 mA/cm.sup.2 at 200 volts. The emitter is robust and the current it produces is not sensitive to variability of vacuum or the distance between the emitter tip and the cathode. The novel emitter has a sharp turn-on near 100 volts.

Zettl, Alexander Karlwalter (Kensington, CA); Cohen, Marvin Lou (Berkeley, CA)

2000-01-01T23:59:59.000Z

252

Magnetron sputtering source  

DOE Patents (OSTI)

A magnetron sputtering source for sputtering coating substrates includes a high thermal conductivity electrically insulating ceramic and magnetically attached sputter target which can eliminate vacuum sealing and direct fluid cooling of the cathode assembly. The magnetron sputtering source design results in greater compactness, improved operating characteristics, greater versatility, and low fabrication cost. The design easily retrofits most sputtering apparatuses and provides for safe, easy, and cost effective target replacement, installation, and removal.

Makowiecki, Daniel M. (Livermore, WA); McKernan, Mark A. (Livermore, CA); Grabner, R. Fred (Brentwood, CA); Ramsey, Philip B. (Livermore, CA)

1994-01-01T23:59:59.000Z

253

Magnetron sputtering source  

DOE Patents (OSTI)

A magnetron sputtering source for sputtering coating substrates includes a high thermal conductivity electrically insulating ceramic and magnetically attached sputter target which can eliminate vacuum sealing and direct fluid cooling of the cathode assembly. The magnetron sputtering source design results in greater compactness, improved operating characteristics, greater versatility, and low fabrication cost. The design easily retrofits most sputtering apparatuses and provides for safe, easy, and cost effective target replacement, installation, and removal. 12 figs.

Makowiecki, D.M.; McKernan, M.A.; Grabner, R.F.; Ramsey, P.B.

1994-08-02T23:59:59.000Z

254

HIGH VOLTAGE ION SOURCE  

DOE Patents (OSTI)

A device is described for providing a source of molecular ions having a large output current and with an accelerated energy of the order of 600 kv. Ions are produced in an ion source which is provided with a water-cooled source grid of metal to effect maximum recombination of atomic ions to molecular ions. A very high accelerating voltage is applied to withdraw and accelerate the molecular ions from the source, and means are provided for dumping the excess electrons at the lowest possible potentials. An accelerating grid is placed adjacent to the source grid and a slotted, grounded accelerating electrode is placed adjacent to the accelerating grid. A potential of about 35 kv is maintained between the source grid and accelerating grid, and a potential of about 600 kv is maintained between the accelerating grid and accelerating electrode. In order to keep at a minimum the large number of oscillating electrons which are created when such high voltages are employed in the vicinity of a strong magnetic field, a plurality of high voltage cascaded shields are employed with a conventional electron dumping system being employed between each shield so as to dump the electrons at the lowest possible potential rather than at 600 kv.

Luce, J.S.

1960-04-19T23:59:59.000Z

255

MILDOS - A Computer Program for Calculating Environmental Radiation Doses from Uranium Recovery Operations  

Science Conference Proceedings (OSTI)

The MILDOS Computer Code estimates impacts from radioactive emissions from uranium milling facilities. These impacts are presented as dose commitments to individuals and the regional population within an 80 km radius of the facility. Only airborne releases of radioactive materials are considered: releases to surface water and to groundwater are not addressed in MILDOS. This code is multi-purposed and can be used to evaluate population doses for NEPA assessments, maximum individual doses for predictive 40 CFR 190 compliance evaluations, or maximum offsite air concentrations for predictive evaluations of 10 CFR 20 compliance. Emissions of radioactive materials from fixed point source locations and from area sources are modeled using a sector-averaged Gaussian plume dispersion model, which utilizes user-provided wind frequency data. Mechanisms such as deposition of particulates, resuspension. radioactive decay and ingrowth of daughter radionuclides are included in the transport model. Annual average air concentrations are computed, from which subsequent impacts to humans through various pathways are computed. Ground surface concentrations are estimated from deposition buildup and ingrowth of radioactive daughters. The surface concentrations are modified by radioactive decay, weathering and other environmental processes. The MILDOS Computer Code allows the user to vary the emission sources as a step function of time by adjustinq the emission rates. which includes shutting them off completely. Thus the results of a computer run can be made to reflect changing processes throughout the facility's operational lifetime. The pathways considered for individual dose commitments and for population impacts are: Inhalation External exposure from ground concentrations External exposure from cloud immersion Ingestioo of vegetables Ingestion of meat Ingestion of milk Dose commitments are calculated using dose conversion factors, which are ultimately based on recommendations of the International Commission on Radiological Protection (ICRP). These factors are fixed internally in the code, and are not part of the input option. Dose commitments which are available from the code are as follows: Individual dose commitments for use in predictive 40 CFR 190 compliance evaluations (Radon and short-lived daughters are excluded) Total individual dose commitments (impacts from all available radionuclides are considered) Annual population dose commitments (regional, extraregional, total and cummulative). This model is primarily designed for uranium mill facilities, and should not be used for operations with different radionuclides or processes.

Strange, D. L.; Bander, T. J.

1981-04-01T23:59:59.000Z

256

Some Calculations for Cold Fusion Superheavy Elements  

E-Print Network (OSTI)

The Q value and optimal exciting energy of the hypothetical superheavy nuclei in cold fusion reaction are calculated with relativistic mean field model and semiemperical shell model mass equation(SSME) and the validity of the two models is tested. The fusion barriers are also calculated with two different models and reasonable results are obtained. The calculations can give useful references for the experiments in the superheavy nuclei synthesized in cold fusion reactions.

X. H. Zhong; L. Li; P. Z. Ning

2004-10-18T23:59:59.000Z

257

New and Underutilized Technology: Commercial Ground Source Heat Pumps |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Commercial Ground Source Heat Commercial Ground Source Heat Pumps New and Underutilized Technology: Commercial Ground Source Heat Pumps October 8, 2013 - 2:59pm Addthis The following information outlines key deployment considerations for commercial ground source heat pumps within the Federal sector. Benefits Commercial ground source heat pumps are ground source heat pump with loops that feed multiple packaged heat pumps and a single ground source water loop. Unit capacity is typically 1-10 tons and may be utilized in an array of multiple units to serve a large load. Application Condensing boilers are appropriate for housing, service, office, and research and development applications. Key Factors for Deployment FEMP has made great progress with commercial ground source heat pump technology deployment within the Federal sector. Primary barriers deal with

258

Inter-sourcing: alternative IT sourcing solutions using student interns  

Science Conference Proceedings (OSTI)

Information Technology (IT) sourcing decisions are motivated by cost savings, skills acquisition, and staffing flexibility. The research in progress introduces a new alternative in sourcing, inter-sourcing. This practice incorporates the benefits of ... Keywords: inter-sourcing, it education, it internships, it sourcing

Mari W. Buche

2013-05-01T23:59:59.000Z

259

Application of Phase Diagram Calculation to Accelerated ...  

Science Conference Proceedings (OSTI)

Presentation Title, Application of Phase Diagram Calculation to Accelerated Development of Mo-Si-B Based Alloys. Author(s), Ying Yang, H Bei, Shuanglin...

260

Multilevel acceleration of neutron transport calculations.  

E-Print Network (OSTI)

??Nuclear reactor design requires the calculation of integral core parameters and power and radiation profiles. These physical parameters are obtained by the solution of the (more)

Marquez Damian, Jose Ignacio

2007-01-01T23:59:59.000Z

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


261

Calculating Cyclotomic Polynomials - CECM - Simon Fraser University  

E-Print Network (OSTI)

algorithm calculates ?n(z) as a quotient of products of sparse power series. ... polynomials and their coefficients available at the Sloane On-Line Encyclopedia ...

262

NREL: Power Technologies Energy Data Book - Calculators  

NLE Websites -- All DOE Office Websites (Extended Search)

Energy Analysis Center Energy Analysis Newsletter Power Technologies Energy Data Book Home Table of Contents Browse by Technology Calculators Renewable Energy Conversion...

263

Building Technologies Office: 179D DOE Calculator  

NLE Websites -- All DOE Office Websites (Extended Search)

Energy simulations are required to show compliance with the energy and power cost savings requirements. View more detailed information. What is the 179D DOE Calculator? The...

264

Using Bayes' Theorem for Free Energy Calculations.  

E-Print Network (OSTI)

??Statistical mechanics is fundamentally based on calculating the probabilities of molecular-scaleevents. Although Bayes theorem has generally been recognized as providing key guiding principals for setup (more)

Rogers, David M.

2009-01-01T23:59:59.000Z

265

Lennard-Jones Fluid Reference Calculations  

Science Conference Proceedings (OSTI)

... The definition of these energetic terms are given ... calculations given here, the following definitions are relevant: ... D. The pair internal energy is given ...

2013-07-12T23:59:59.000Z

266

The Materials Project: Combining Quantum Chemistry Calculations...  

NLE Websites -- All DOE Office Websites (Extended Search)

The Materials Project: Combining Quantum Chemistry Calculations with Supercomputing Centers for New Materials Discovery Speaker(s): Anubhav Jain Date: December 18, 2012 - 12:00pm...

267

MatCalc - The Materials Calculator  

Science Conference Proceedings (OSTI)

Oct 12, 2007 ... MatCalc is supported on Windows, Linux, and Mac OSX systems. Citation: " MatCalc - The Materials Calculator." MatCalc (2008).

268

Building Technologies Office: Qualified Software for Calculating...  

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

you'll find a list of qualified computer software for calculating commercial building energy and power cost savings that meet federal tax incentive requirements. To submit...

269

Drag calculations improve efficiency of hydraulic jars  

Science Conference Proceedings (OSTI)

Using drag calculations helps accurately determine the maximum hook load for optimal over-pull force during jarring operations. The driller then has a better chance of freeing stuck pipe on the first jarring attempt. Several operational situations demonstrate how these calculations allow the over pull force on the jar during operation to be increased by 40 % compared to calculations involving the weight of the drillstring only. The drag calculation method significantly increases the probability of successful jarring operations. This article concentrates on upward jarring; the results and procedures are applicable, however, for downward jarring as well.

Aarrestad, T.V. (Den norske stats oljeselskap AS, Statoil (Norway))

1993-03-29T23:59:59.000Z

270

Table 7.9 Expenditures for Purchased Energy Sources, 2002  

U.S. Energy Information Administration (EIA) Indexed Site

9 Expenditures for Purchased Energy Sources, 2002;" 9 Expenditures for Purchased Energy Sources, 2002;" " Level: National and Regional Data;" " Row: NAICS Codes; Column: Energy Sources;" " Unit: Million U.S. Dollars." " "," "," ",," "," "," "," "," "," "," "," ",," " " "," ",,,,,,,,,,"RSE" "NAICS"," "," ",,"Residual","Distillate","Natural ","LPG and",,"Coke"," ","Row" "Code(a)","Subsector and Industry","Total","Electricity","Fuel Oil","Fuel Oil(b)","Gas(c)","NGL(d)","Coal","and Breeze","Other(e)","Factors"

271

The influence of material models on chemical or nuclear-explosion source functions  

SciTech Connect

Physical models of explosion sources are needed to explain the variations in the performance of existing discriminants in different regions, and to help develop more robust methods for identifying underground explosions. In this paper, we assess the sensitivity of explosion source functions to material properties by means of numerical simulations. Specifically, we have calculated the effect of varying the yield strength, overburden pressure, and gas porosity on the spectra of the reduced velocity potential for both nuclear and chemical explosions, and compared these with experimental results derived from free-field particle acceleration and regional seismic (LNN) data. The chemical-explosion calculations were intended to simulate the kiloton experiment recently conducted in Area 12 of the Nevada Test Site (NTS) that has been dubbed the Non-Proliferation Experiment (NPE). We found that the asymptotic (long period) value of the reduced displacement potential, {phi}{infinity}, for explosions with the ANFO blasting agent used in the NPE, was larger than that derived for a tamped nuclear explosion of the same yield by a factor of 1.9, in good agreement with the experimental results derived from free-field particle velocity measurements, and also with m{sub b}(P{sub n}) data from the Livermore Nevada Network (LNN).

Glenn, L.A.; Goldstein, P.

1994-04-01T23:59:59.000Z

272

Semiclassical calculation of photon-stimulated Schwinger pair creation  

Science Conference Proceedings (OSTI)

We consider the electron-positron pair creation by a photon in an external constant electric field. The presented treatment is based on a purely quasiclassical calculation of the imaginary part of the on-shell photon polarization operator. By using this approach we find the pair production rate for photons with polarization parallel as well as orthogonal to the external electric field in the leading order in the parameter eE/m{sup 2}, which has been recently found by other methods. For the orthogonal polarization we also find a new contribution to the rate, which is leading in the ratio of the photon energy to the electron mass {omega}/m. We also reproduce by a purely geometrical calculation the exponential factor in the probability of the stimulated pair creation at arbitrary energy of the photon.

Monin, A.; Voloshin, M. B. [School of Physics and Astronomy, University of Minnesota, Minneapolis, Minnesota 55455 (United States); William I. Fine Theoretical Physics Institute, University of Minnesota, Minneapolis, Minnesota 55455 (United States)

2010-04-15T23:59:59.000Z

273

Estimating carbon dioxide emissions factors for the California electric power sector  

E-Print Network (OSTI)

Energy Data Report; emissions from imports calculated using U.S.source of energy in the Southwest U.S. Thus, imports from

Marnay, Chris; Fisher, Diane; Murtishaw, Scott; Phadke, Amol; Price, Lynn; Sathaye, Jayant

2002-01-01T23:59:59.000Z

274

Heat Source Lire,  

NLE Websites -- All DOE Office Websites (Extended Search)

Source Lire, Source Lire, (liayrICS-25 ) tooling Tulles (Ai 1,06:1) - 11 (31.118 Module Stack Thermoelectric Module:, (14) ltcal L/Mr r a it i lli tisli Block Mounting Interface MMRTG Design Housing (At 2219) Fin (At Go63) Thermal Insulation (Min-K & Microtherm) Space Radioisotope Power Systems Multi-Mission Radioisotope Thermoelectric Generator January 2008 What is a Multi-Mission Radioisotope Thermoelectric Generator? Space exploration missions require safe, reliable, long-lived power systems to provide electricity and heat to spacecraft and their science instruments. A uniquely capable source of power is the radioisotope thermoelectric generator (RTG) - essentially a nuclear battery that reliably converts heat into electricity. The Department of Energy and NASA are developing

275

Source Selection Guide  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Source Selection Source Selection Overview This chapter provides guidance to the acquisition team on conducting source selection in accordance with Part 15 of the Federal Acquisition Regulation (FAR). Background The mid 1990's was a time of significant change in many areas of procurement, particularly in the introduction of new tools and processes that help the procurement professional better meet the needs of demanding customers. The passage of the Federal Acquisition Streamlining Act in 1994 and the Federal Acquisition Reform Act in 1995 , coupled with Government-wide and Department of Energy (DOE) contract reform efforts not only changed traditional procurement processes but also changed the role of the procurement professional. No longer are procurement

276

ISG8-RF Sources  

NLE Websites -- All DOE Office Websites (Extended Search)

RF Sources - (WG3) RF Sources - (WG3) Orange Rm Yong Ho Chin, Christopher Nantista, and Sami G. Tantawi Parallel Sessions: Working Groups: WG1: Parameters, Design, Instrumentation and Tuning WG2: Damping Rings and ATF WG3: RF Sources WG4:Structures WG5: Ground Motion; Site Requirements and Investigations Monday Morning 9:00-10:30 Plenary Coffee Break 11:00-12:00 Planning Session. Monday Afternoon 13:30-15:30 High Gradient Issues (Joint with working group 4) Coffee Break 16:00-16:30 The 8-Pack Project -- D. Atkinson 16:30-17:30 High Gradient Issues and Discussions Continued. Tuesday Morning 9:30-10:30 Klystrons 9:30-10:00 Status of PPM Klystron Development for JLC -- Y. H. Chin 10:00-10:30 Design of 150MW Multi-Beam Klystron -- S. Matsumoto Coffee Break 11:00-11:30 Klystron Development at SLAC -- G. Caryotakis

277

Dual source heat pump  

DOE Patents (OSTI)

What is disclosed is a heat pump apparatus for conditioning a fluid characterized by a fluid handler and path for circulating the fluid in heat exchange relationship with a refrigerant fluid; at least two refrigerant heat exchangers, one for effecting heat exchange with the fluid and a second for effecting heat exchange between refrigerant and a heat exchange fluid and the ambient air; a compressor for efficiently compressing the refrigerant; at least one throttling valve for throttling liquid refrigerant; a refrigerant circuit; refrigerant; a source of heat exchange fluid; heat exchange fluid circulating device and heat exchange fluid circuit for circulating the heat exchange fluid in heat exchange relationship with the refrigerant; and valves or switches for selecting the heat exchangers and direction of flow of the refrigerant therethrough for selecting a particular mode of operation. The heat exchange fluid provides energy for defrosting the second heat exchanger when operating in the air source mode and also provides a alternate source of heat.

Ecker, Amir L. (Dallas, TX); Pietsch, Joseph A. (Dallas, TX)

1982-01-01T23:59:59.000Z

278

Photon Source Parameters  

NLE Websites -- All DOE Office Websites (Extended Search)

Photon Source Parameters Photon Source Parameters Photon Source Parameters Print Summary Graph of Brightness Curves for All Insertion Devices Insertion Device and Bend Magnet Parameters Bend Magnet Superbend Magnet U30 Undulator U50 Undulator U80 Undulator U100 Undulator W114 Wiggler The ALS has six elliptically polarizing undulators, two in straight 4, two in straight 11, and one each in straights 6 and 7. All are arranged with chicanes so that two such devices can be installed to feed two independent beamlines. They can be used in a variety of polarization modes, including circular, elliptical, horizontal, and vertical. These modes can be chosen by appropriate phasing of the magnet rows. The brightness and flux curves below are shown for horizontal and circular polarization. Curves for elliptical and vertical polarization are similar to the horizontal polarization curve, but the minimum photon energy is higher.

279

Source Emissions and Transport  

NLE Websites -- All DOE Office Websites (Extended Search)

electron micrograph image, Lara Gundel with instrumentation electron micrograph image, Lara Gundel with instrumentation Source Emissions and Transport Investigators conduct research here to characterize and better understand the sources of airborne volatile, semi-volatile and particulate organic pollutants in the indoor environment. This research includes studies of the physical and chemical processes that govern indoor air pollutant concentrations and exposures. The motivation is to contribute to the reduction of potential human health effects. Contacts Randy Maddalena RLMaddalena@lbl.gov (510) 486-4924 Mark Mendell MJMendell@lbl.gov (510) 486-5762 Links Pollutant Sources, Dynamics and Chemistry Group Batteries and Fuel Cells Buildings Energy Efficiency Electricity Grid Energy Analysis Energy Technologies Environmental Impacts

280

Parametric HECTR calculations of hydrogen transport and combustion at N Reactor  

DOE Green Energy (OSTI)

This report describes a limited number of parametric calculations of hydrogen transport and combustion in the N Reactor confinement for selected accident sequences. The calculations are performed using the HECTR computer code, which is a lumped-parameter code developed specifically for evaluating hydrogen behavior in reactor containments. A number of parameters are evaluated in this study, including hydrogen source rate, spray effects, and source location. The calculations indicate that mixing within major compartments tends to occur fairly rapidly, but that mixing between compartments can be inhibited in certain situations, resulting in the formation of flammable mixtures. These results are being compared to calculations performed with other computer codes, including a code that uses finite-difference models. United Nuclear Corporation will present the results of these code comparisons in future reports.

Payne, A.C. Jr.; Camp, A.L.

1987-06-01T23:59:59.000Z

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


281

PVWatts (R) Calculator India (Fact Sheet)  

SciTech Connect

The PVWatts (R) Calculator for India was released by the National Renewable Energy Laboratory in 2013. The online tool estimates electricity production and the monetary value of that production of grid-connected roof- or ground-mounted crystalline silicon photovoltaics systems based on a few simple inputs. This factsheet provides a broad overview of the PVWatts (R) Calculator for India.

Not Available

2014-01-01T23:59:59.000Z

282

Numerical Object Oriented Quantum Field Theory Calculations  

E-Print Network (OSTI)

The qft++ package is a library of C++ classes that facilitate numerical (not algebraic) quantum field theory calculations. Mathematical objects such as matrices, tensors, Dirac spinors, polarization and orbital angular momentum tensors, etc. are represented as C++ objects in qft++. The package permits construction of code which closely resembles quantum field theory expressions, allowing for quick and reliable calculations.

M. Williams

2008-05-19T23:59:59.000Z

283

Data base to compare calculations and observations  

Science Conference Proceedings (OSTI)

Meteorological and climatological data bases were compared with known tritium release points and diffusion calculations to determine if calculated concentrations could replace measure concentrations at the monitoring stations. Daily tritium concentrations were monitored at 8 stations and 16 possible receptors. Automated data retrieval strategies are listed. (PSB)

Tichler, J.L.

1985-01-01T23:59:59.000Z

284

Proper Orthogonal Decomposition for Flow Calculations  

E-Print Network (OSTI)

Proper Orthogonal Decomposition for Flow Calculations and Optimal Control in a Horizontal CVD calculations are discussed. AMS Subject Classification: 76N10, 65K10, 49J20 & 35C10 \\Lambda This research a chemical reaction in the gas phase above the surface of the film to deposit desired materials onto

285

INEEL Source Water Assessment  

SciTech Connect

The Idaho National Engineering and Environmental Laboratory (INEEL) covers approximately 890 mi2 and includes 12 public water systems that must be evaluated for Source water protection purposes under the Safe Drinking Water Act. Because of its size and location, six watersheds and five aquifers could potentially affect the INEELs drinking water sources. Based on a preliminary evaluation of the available information, it was determined that the Big Lost River, Birch Creek, and Little Lost River Watersheds and the eastern Snake River Plain Aquifer needed to be assessed. These watersheds were delineated using the United States Geologic Surveys Hydrological Unit scheme. Well capture zones were originally estimated using the RESSQC module of the Environmental Protection Agencys Well Head Protection Area model, and the initial modeling assumptions and results were checked by running several scenarios using Modflow modeling. After a technical review, the resulting capture zones were expanded to account for the uncertainties associated with changing groundwater flow directions, a thick vadose zone, and other data uncertainties. Finally, all well capture zones at a given facility were merged to a single wellhead protection area at each facility. A contaminant source inventory was conducted, and the results were integrated with the well capture zones, watershed and aquifer information, and facility information using geographic information system technology to complete the INEELs Source Water Assessment. Of the INEELs 12 public water systems, three systems rated as low susceptibility (EBR-I, Main Gate, and Gun Range), and the remainder rated as moderate susceptibility. No INEEL public water system rated as high susceptibility. We are using this information to develop a source water management plan from which we will subsequently implement an INEEL-wide source water management program. The results are a very robust set of wellhead protection areas that will protect the INEELs public water systems yet not too conservative to inhibit the INEEL from carrying out its missions.

Sehlke, Gerald

2003-03-01T23:59:59.000Z

286

Photon Source Parameters  

NLE Websites -- All DOE Office Websites (Extended Search)

Note: Brightness and flux were calculated at a machine energy of 1.9 GeV, 500 mA current, vertical emittance of 40 x 10-12 mrad, horizontal emittance of 2.0 x 10-9 mrad,...

287

FABRICATION OF NEUTRON SOURCES  

DOE Patents (OSTI)

A method is presented for preparing a neutron source from polonium-210 and substances, such as beryllium and boron, characterized by emission of neutrons upon exposure to alpha particles from the polonium. According to the invention, a source is prepared by placing powdered beryllium and a platinum foil electroplated with polonium-2;.0 in a beryllium container. The container is sealed and then heated by induction to a temperature of 450 to 1100 deg C to volatilize the polonium off the foil into the powder. The heating step is terminated upon detection of a maximum in the neutron flux level.

Birden, J.H.

1959-04-21T23:59:59.000Z

288

China 2050 Pathways Calculator | Open Energy Information  

Open Energy Info (EERE)

China 2050 Pathways Calculator China 2050 Pathways Calculator Jump to: navigation, search Tool Summary LAUNCH TOOL Name: China 2050 Pathways Calculator Agency/Company /Organization: China's Energy Research Institute (ERI), UK Department of Energy and Climate Change (DECC), UK Foreign and Commonwealth Office (FCO) Focus Area: Non-renewable Energy, Renewable Energy Phase: Evaluate Options, Prepare a Plan Topics: Low-carbon plans/TNAs/NAMAs, Resource assessment, Pathways analysis Resource Type: Guide/manual, Training materials, Lessons learned/best practices, Online calculator User Interface: Website Website: china-en.2050calculator.net/pathways/111011011011101101011010111101101 Country: China OpenEI Keyword(s): International Eastern Asia Language: English References: Global Energy Governance Reform, 3 October 2012[1]

289

CUFR Tree Carbon Calculator | Open Energy Information  

Open Energy Info (EERE)

CUFR Tree Carbon Calculator CUFR Tree Carbon Calculator Jump to: navigation, search Tool Summary LAUNCH TOOL Name: CUFR Tree Carbon Calculator Agency/Company /Organization: United States Forest Service Sector: Climate, Land Focus Area: Forestry Phase: Determine Baseline, Evaluate Options Topics: GHG inventory, Resource assessment Resource Type: Software/modeling tools User Interface: Desktop Application Website: www.fs.fed.us/ccrc/topics/urban-forests/ctcc/ Cost: Free Language: English References: CUFR Tree Carbon Calculator[1] Overview "The CUFR Tree Carbon Calculator is the only tool approved by the Climate Action Reserve's Urban Forest Project Protocol for quantifying carbon dioxide sequestration from GHG tree planting projects. The CTCC is programmed in an Excel spreadsheet and provides carbon-related information

290

Campus Carbon Calculator | Open Energy Information  

Open Energy Info (EERE)

Campus Carbon Calculator Campus Carbon Calculator Jump to: navigation, search Tool Summary Name: Campus Carbon Calculator Agency/Company /Organization: Clean Air-Cool Planet Phase: Create a Vision, Determine Baseline, Develop Goals User Interface: Spreadsheet Website: www.cleanair-coolplanet.org/toolkit/inv-calculator.php The Campus Carbon Calculator(tm), Version 6.4, is now available for download. Version 6.4 includes new features, updates and corrections - including greatly expanded projection and solutions modules, designed to aid schools that have completed greenhouse gas inventories in developing long term, comprehensive climate action plans based on those inventories. The new modules facilitate analysis of carbon reduction options, determining project payback times, net present value, cost per ton reduced,

291

Identifying PM10 Sources and Estimating Source Contributions...  

NLE Websites -- All DOE Office Websites (Extended Search)

of ammonium nitric, secondary aerosol of ammonium sulfate, and incinerator and fuel oil burning sources. The source mass profiles derived by the PMF model well describe the...

292

Life Management of Creep Strength Enhanced Grade 91 Steel: Damage Calculator  

Science Conference Proceedings (OSTI)

Creep damage depends on stress, temperature, and material. This project established a database of creep data for Grade 91 steels and reviewed representative materials relationships that provide a best fit to the database. The relationships from several expert sources have been used in a Microsoft Excel-based damage calculator. This calculator allows comparison of component performance for selected operating conditions and material creep properties. The approach facilitates comparison of life ...

2013-06-20T23:59:59.000Z

293

Composition, sources, and formation of secondary organic aerosols from urban emissions  

E-Print Network (OSTI)

mixtures from biomass burning and combustion sources forburning, northeast and combustion, biomass burning, factorresulted in biomass burning and combustion type factors.

Liu, Shang; Liu, Shang

2012-01-01T23:59:59.000Z

294

Shielding Calculations for the Hard X-Rays Generated by LCLS Mec Laser System  

Science Conference Proceedings (OSTI)

Linac Coherent Light Source (LCLS) Matter in Extreme Conditions (MEC) Instrument is an X-ray instrument that will be able to create and diagnose High Energy Density (HED) matter. The MEC laser system can generate hard X-ray due to the interaction of the laser and the plasma. This paper summarizes results of the shielding calculations performed to evaluate the radiation hazards induced by this hard X-ray source with Monte Carlo code FLUKA. The dose rates and photon spectra due to this X-ray source are calculated at different locations with different shielding. The influence of the electron temperature on the source terms and the shielding effectiveness was also investigated.

Not Available

2011-06-02T23:59:59.000Z

295

Spent N fuel project preliminary saftey evaluation of the cold vacuum drying system -- calculations for the flammable gas ignition scenario  

DOE Green Energy (OSTI)

For a preliminary safety evaluation of the Cold Vacuum Drying System, calculations for the flammable gas ignition scenario are provided. Hydrogen buildup from uranium corrosion in the MCO followed by inadvertent injection of oxygen and the presence of an ignition source leads to hydrogen deflagration that over pressurizes and releases radioactive particulate matter to the environment. The adiabatic flame temperature, MCO pressure and source term are calculated.

Scott, D.L.

1996-06-12T23:59:59.000Z

296

COMBUSTION SOURCES OF NITROGEN COMPOUNDS  

E-Print Network (OSTI)

Rasmussen, R.A. (1976). Combustion as a source of nitrousx control for stationary combustion sources. Prog. Energy,CA, March 3-4, 1977 COMBUSTION SOURCES OF NITROGEN COMPOUNDS

Brown, Nancy J.

2011-01-01T23:59:59.000Z

297

Conversion factors for energy equivalents: All factors  

Science Conference Proceedings (OSTI)

... Conversion factors for energy equivalents Return to online conversions. Next page of energy equivalents. Definition of uncertainty ...

298

Selective ion source  

DOE Patents (OSTI)

A ion source is described wherein selected ions maybe extracted to the exclusion of unwanted ion species of higher ionization potential. Also described is a method of producing selected ions from a compound, such as P.sup.+ from PH.sub.3. The invention comprises a plasma chamber, an electron source, a means for introducing a gas to be ionized by electrons from the electron source, means for limiting electron energy from the electron source to a value between the ionization energy of the selected ion species and the greater ionization energy of an unwanted ion specie, and means for extracting the target ion specie from the plasma chamber. In one embodiment, the electrons are generated in a plasma cathode chamber immediately adjacent to the plasma chamber. A small extractor draws the electrons from the plasma cathode chamber into the relatively positive plasma chamber. The energy of the electrons extracted in this manner is easily controlled. The invention is particularly useful for doping silicon with P.sup.+, AS.sup.+, and B.sup.+ without the problematic presence of hydrogen, helium, water, or carbon oxide ions. Doped silicon is important for manufacture of semiconductors and semiconductor devices.

Leung, Ka-Ngo (Hercules, CA)

1996-01-01T23:59:59.000Z

299

Use of multiple 4$pi$ radiation sources for quasi-uniform irradiation of square surfaces  

SciTech Connect

The question of distance and location of multiple 4 pi radiation sources from square planar target surfaces is addressed, with the constraint that the surface be irradiated with 80% uniformity. Results of computer calculations are presented, giving source location coordinates for optimum use of the sources under the uniformity constraint. (auth)

Clark, R.W.; Freiwald, D.A.

1973-11-01T23:59:59.000Z

300

Nonequilibrium molecular dynamics simulation of shear viscosity by a uniform momentum source-and-sink scheme  

Science Conference Proceedings (OSTI)

A uniform momentum source-and-sink scheme of nonequilibrium molecular dynamics (NEMD) is developed to calculate the shear viscosity of fluids in this paper. The uniform momentum source and sink are realized by momentum exchanges of individual atoms in ... Keywords: Molecular fluid, Nonequilibrium molecular dynamics, Shear viscosity, Uniform source-and-sink scheme

Bing-Yang Cao; Ruo-Yu Dong

2012-06-01T23:59:59.000Z

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


301

Foodborne Illness Cost Calculator | Data.gov  

NLE Websites -- All DOE Office Websites (Extended Search)

Foodborne Illness Cost Calculator Foodborne Illness Cost Calculator Agriculture Community Menu DATA APPS EVENTS DEVELOPER STATISTICS COLLABORATE ABOUT Agriculture You are here Data.gov » Communities » Agriculture » Data Foodborne Illness Cost Calculator Dataset Summary Description The calculator provides information on the assumptions behind foodborne illness cost estimates and gives you a chance to make your own assumptions and calculate your own cost estimates. This interactive web-based tool allows users to estimate the cost of illness due to specific foodborne pathogens. The updated ERS cost estimate for Shiga-toxin producing E. coli O157 (STEC O157) was added to the Calculator in spring, 2008. Calculator users can now review and change the assumptions behind the ERS cost estimates for either STEC O157 or Salmonella. The assumptions that can be modified include the annual number of cases, the distribution of cases by severity, the use or costs of medical care, the amount or value of time lost from work, the costs of premature death, and the disutility costs for nonfatal cases. Users can also update the cost estimate for inflation for any year from 1997 to 2007.

302

Strategic Sourcing | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Strategic Sourcing Strategic Sourcing Strategic Sourcing Energy Wide Strategic Sourcing (EWSS) DOE leadership has recognized that benefits could be achieved at the federal level through an organized, systematic and collaborative approach to acquiring commonly used goods and services. The DOE strategic sourcing program builds upon historical accomplishments as well as establishes a more cohesive and disciplined program, consistent with OMB's direction, for the conduct of DOE future strategic sourcing efforts. The DOE and NNSA Senior Procurement Executives have created a strategic sourcing capability and organizational components to identify federal strategic sourcing opportunities and coordinate strategic thinking. To date, this program has identified a number of opportunities; particularly in the areas of

303

WIPP Opportunities - Procurement - Sources Sought  

NLE Websites -- All DOE Office Websites (Extended Search)

Procurement Sources Sought This page displays a listing Sources Sought. If you are interested in submitting an outline, please contact the cognizant buyer to find out more. Please...

304

Book sources | Open Energy Information  

Open Energy Info (EERE)

Community Linked Data Special page Share this page on Facebook icon Twitter icon Book sources Jump to: navigation, search Search for book sources ISBN: Go Retrieved from...

305

Book sources | Open Energy Information  

Open Energy Info (EERE)

Community Linked Data Special page Share this page on Facebook icon Twitter icon Book sources Jump to: navigation, search Search for book sources ISBN: 9781603580304 Go...

306

Energy Sources | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Sources Energy Sources Renewable Energy Learn more about Solar, Water, Biomass, Geothermal and Wind Energy. Read more Nuclear Learn more about how we use Nuclear Energy. Read more...

307

Energy Sources | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Science & Innovation Energy Sources Energy Sources Renewable Energy Learn more about Solar, Water, Biomass, Geothermal and Wind Energy. Read more Nuclear Learn more about how we...

308

Improved operation of the nonambipolar electron source  

Science Conference Proceedings (OSTI)

Significant improvements have been made to the nonambipolar electron source (NES), a radio frequency (rf) plasma-based electron source that does not rely on electron emission at a cathode surface [B. Longmier, S. Baalrud, and N. Hershkowitz, Rev. Sci. Instrum. 77, 113504 (2006)]. A prototype NES has produced 30 A of continuous electron current, using 2 SCCM (SCCM denotes cubic centimeter per minute at STP) Xe, 1300 W rf power at 13.56 MHz, yielding a 180 times gas utilization factor. A helicon mode transition has also been identified during NES operation with an argon propellant, using 15 SCCM Ar, 1000 W rf, and 100 G magnetic field. This NES technology has the ability to replace hollow cathode electron sources and to enable high power electric propulsion missions, eliminating one of the lifetime restrictions that many ion thrusters have previously been faced with.

Longmier, Ben; Hershkowitz, Noah [University of Wisconsin-Madison, Madison, Wisconsin 53706 (United States)

2008-09-15T23:59:59.000Z

309

Radiation-damage calculations with NJOY  

SciTech Connect

Atomic displacement, gas production, transmutation, and nuclear heating can all be calculated with the NJOY nuclear data processing system using evaluated data in ENDF/B format. Using NJOY helps assure consistency between damage cross sections and those used for transport, and NJOY provides convenient interface formats for linking data to application codes. Unique features of the damage calculation include a simple momentum balance treatment for radiative capture and a new model for (n, particle) reactions based on statistical model calculations. Sample results for iron and nickel are given and compared with the results of other methods.

MacFarlane, R.E.; Muir, D.W.; Mann, F.W.

1983-01-01T23:59:59.000Z

310

Calculating the Diffuse Responsivity of Solar Pyranometers  

DOE Green Energy (OSTI)

Pyranometers are used to measure the global and diffuse components of solar irradiance. One of the methods to calculate the unshade (global) responsivity of a pyranometer is the standard shading method, described in the Annual Book of ASTM Standards, section 14, volume 14.02. In this paper, the standard method is used to calculate the shade (diffuse) responsivity of a pyranometer by accounting for the zenith and azimuth response of the pyranometer. A discussion of the effect of pyranometer offset on the calculated responsivity is also presented.

Reda, I.; Myers, D.

1999-08-16T23:59:59.000Z

311

Estimating carbon dioxide emission factors for the California electric power sector  

SciTech Connect

The California Climate Action Registry (''Registry'') was initially established in 2000 under Senate Bill 1771, and clarifying legislation (Senate Bill 527) was passed in September 2001. The Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab) has been asked to provide technical assistance to the California Energy Commission (CEC) in establishing methods for calculating average and marginal electricity emissions factors, both historic and current, as well as statewide and for sub-regions. This study is exploratory in nature. It illustrates the use of three possible approaches and is not a rigorous estimation of actual emissions factors. While the Registry will ultimately cover emissions of all greenhouse gases (GHGs), presently it is focusing on carbon dioxide (CO2). Thus, this study only considers CO2, which is by far the largest GHG emitted in the power sector. Associating CO2 emissions with electricity consumption encounters three major complications. First, electricity can be generated from a number of different primary energy sources, many of which are large sources of CO2 emissions (e.g., coal combustion) while others result in virtually no CO{sub 2} emissions (e.g., hydro). Second, the mix of generation resources used to meet loads may vary at different times of day or in different seasons. Third, electrical energy is transported over long distances by complex transmission and distribution systems, so the generation sources related to electricity usage can be difficult to trace and may occur far from the jurisdiction in which that energy is consumed. In other words, the emissions resulting from electricity consumption vary considerably depending on when and where it is used since this affects the generation sources providing the power. There is no practical way to identify where or how all the electricity used by a certain customer was generated, but by reviewing public sources of data the total emission burden of a customer's electricity supplier can b e found and an average emissions factor (AEF) calculated. These are useful for assigning a net emission burden to a facility. In addition, marginal emissions factors (MEFs) for estimating the effect of changing levels of usage can be calculated. MEFs are needed because emission rates at the margin are likely to diverge from the average. The overall objective of this task is to develop methods for estimating AEFs and MEFs that can provide an estimate of the combined net CO2 emissions from all generating facilities that provide electricity to California electricity customers. The method covers the historic period from 1990 to the present, with 1990 and 1999 used as test years. The factors derived take into account the location and time of consumption, direct contracts for power which may have certain atypical characteristics (e.g., ''green'' electricity from renewable resources), resource mixes of electricity providers, import and export of electricity from utility owned and other sources, and electricity from cogeneration. It is assumed that the factors developed in this way will diverge considerably from simple statewide AEF estimates based on standardized inventory estimates that use conventions inconsistent with the goals of this work. A notable example concerns the treatment of imports, which despite providing a significant share of California's electricity supply picture, are excluded from inventory estimates of emissions, which are based on geographical boundaries of the state.

Marnay, Chris; Fisher, Diane; Murtishaw, Scott; Phadke, Amol; Price, Lynn; Sathaye, Jayant

2002-08-01T23:59:59.000Z

312

Estimating carbon dioxide emission factors for the California electric power sector  

SciTech Connect

The California Climate Action Registry (''Registry'') was initially established in 2000 under Senate Bill 1771, and clarifying legislation (Senate Bill 527) was passed in September 2001. The Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab) has been asked to provide technical assistance to the California Energy Commission (CEC) in establishing methods for calculating average and marginal electricity emissions factors, both historic and current, as well as statewide and for sub-regions. This study is exploratory in nature. It illustrates the use of three possible approaches and is not a rigorous estimation of actual emissions factors. While the Registry will ultimately cover emissions of all greenhouse gases (GHGs), presently it is focusing on carbon dioxide (CO2). Thus, this study only considers CO2, which is by far the largest GHG emitted in the power sector. Associating CO2 emissions with electricity consumption encounters three major complications. First, electricity can be generated from a number of different primary energy sources, many of which are large sources of CO2 emissions (e.g., coal combustion) while others result in virtually no CO{sub 2} emissions (e.g., hydro). Second, the mix of generation resources used to meet loads may vary at different times of day or in different seasons. Third, electrical energy is transported over long distances by complex transmission and distribution systems, so the generation sources related to electricity usage can be difficult to trace and may occur far from the jurisdiction in which that energy is consumed. In other words, the emissions resulting from electricity consumption vary considerably depending on when and where it is used since this affects the generation sources providing the power. There is no practical way to identify where or how all the electricity used by a certain customer was generated, but by reviewing public sources of data the total emission burden of a customer's electricity supplier can b e found and an average emissions factor (AEF) calculated. These are useful for assigning a net emission burden to a facility. In addition, marginal emissions factors (MEFs) for estimating the effect of changing levels of usage can be calculated. MEFs are needed because emission rates at the margin are likely to diverge from the average. The overall objective of this task is to develop methods for estimating AEFs and MEFs that can provide an estimate of the combined net CO2 emissions from all generating facilities that provide electricity to California electricity customers. The method covers the historic period from 1990 to the present, with 1990 and 1999 used as test years. The factors derived take into account the location and time of consumption, direct contracts for power which may have certain atypical characteristics (e.g., ''green'' electricity from renewable resources), resource mixes of electricity providers, import and export of electricity from utility owned and other sources, and electricity from cogeneration. It is assumed that the factors developed in this way will diverge considerably from simple statewide AEF estimates based on standardized inventory estimates that use conventions inconsistent with the goals of this work. A notable example concerns the treatment of imports, which despite providing a significant share of California's electricity supply picture, are excluded from inventory estimates of emissions, which are based on geographical boundaries of the state.

Marnay, Chris; Fisher, Diane; Murtishaw, Scott; Phadke, Amol; Price, Lynn; Sathaye, Jayant

2002-08-01T23:59:59.000Z

313

Use of additional fission sources or scattering sources to model inward axial leakages in fast-reactor analysis  

Science Conference Proceedings (OSTI)

When calculations of flux are done in less than three dimensions, bucklings are normally used to model leakages (flows) in the dimensions for which the flux is not calculated. If the net leakage for a given energy group is outward (positive), the buckling is positive, and buckling methods work well. However, if the new leakage for a given energy group is inward (negative), the buckling is negative and can lead to numerical instabilities (oscillations in the iterative flux calculation). This report discusses two equivalent nonbuckling methods to model inward leakages. One method (the chi/sub g/ method) models these incoming neutrons by additional fission sources. The other method (the ..sigma../sub s/(1 ..-->.. g) method) models them by increased downscatter sources. The derivation of the two methods is shown, and the flux spectra obtained by their use are compared with those obtained from two-dimensional (RZ) calculations.

Grimm, K.N.; Meneghetti, D.

1981-10-01T23:59:59.000Z

314

Algorithm for Building a Spectrum for NREL's One-Sun Multi-Source Simulator: Preprint  

DOE Green Energy (OSTI)

Historically, the tools used at NREL to compensate for the difference between a reference spectrum and a simulator spectrum have been well-matched reference cells and the application of a calculated spectral mismatch correction factor, M. This paper describes the algorithm for adjusting the spectrum of a 9-channel fiber-optic-based solar simulator with a uniform beam size of 9 cm square at 1-sun. The combination of this algorithm and the One-Sun Multi-Source Simulator (OSMSS) hardware reduces NREL's current vs. voltage measurement time for a typical three-junction device from man-days to man-minutes. These time savings may be significantly greater for devices with more junctions.

Moriarty, T.; Emery, K.; Jablonski, J.

2012-06-01T23:59:59.000Z

315

Source term characterization for SNM pit storage facilities  

Science Conference Proceedings (OSTI)

In order to properly design a mobile system to validate and verify the presence of special nuclear materials for non-proliferation and safeguards applications, accurate modeling of source materials is imperative. In this work, models were developed for use in design assessments based on an AL-R8 SNM standardized container specification to determine the radioactive signatures for both highly enriched uranium (HEU) and weapons plutonium (WGPu) special nuclear materials (SNM) housed in the containers. Intrinsic gamma boundary leakage currents were evaluated for this system, performed using 3D fixed-source deterministic SN photon transport (PENTRAN) as well as with stochastic Monte Carlo methods (MCNP5). Group-dependent leakage radiation terms were calculated at two 'source box' interfaces within the models, one directly surrounding the SNM source, and one immediately surrounding the canister. Analysis showed good agreement between the two models for energy groups of interest, based on a 24 group gamma library established for HEU and WGPu gamma signatures of interest. Intrinsic and neutron induced gamma leakage was determined using Monte Carlo calculations, and the combined gamma signatures were then treated as a net gamma leakage to be used in subsequent photon transport calculations. Neutron leakage based on the BUGLE-96 47 group structure was determined using Monte Carlo calculations for the WGPu canisters. These results will be used to evaluate the source term from stored nuclear materials and augment our efforts to design a detection system to validate the presence of these materials for safeguards purposes. (authors)

Chin, M.; Paul, J.; Sjoden, G. [Nuclear and Radiological Engineering Program, George W. Woodruff School of Mechanical Engineering, Georgia Inst. of Technology, 770 State St, Atlanta, GA 30332-0745 (United States)

2012-07-01T23:59:59.000Z

316

3D calculations of a fixed field alternating gradient synchrotron magnet  

SciTech Connect

A Spallation neutron source for materials science studies was designed at Argonne and required a fixed field alternating gradient (FFAG) synchrotron magnet. 3D electrostatic calculations were made to obtain the unsaturated magnet pole shape. This pole shape was refined using 3D magnetostatic calculations that included the steel permeability and coil geometry. Details of the calculations are given concerning such things as: size of the problem and how to split it up, the number and shape of the finite elements, choosing the electrostatic potential correctly and selecting the potential of the desired pole. 5 figs.

Lari, R.J.

1985-01-01T23:59:59.000Z

317

Assessment of New Calculation Method for Toxicological Sums-of-Fractions for Hanford Tank Farm Wastes  

SciTech Connect

The toxicological source terms used for potential accident assessment in the Hanford Tank Farms DSA are based on toxicological sums-of-fractions (SOFs) that were calculated based on the Best Basis Inventory (BBI) from May 2002, using a method that depended on thermodynamic equilibrium calculations of the compositions of liquid and solid phases. The present report describes a simplified SOF-calculation method that is to be used in future toxicological updates and assessments and compares its results (for the 2002 BBI) to those of the old method.

Mahoney, Lenna A.

2006-10-18T23:59:59.000Z

318

Urban Transportation Emission Calculator | Open Energy Information  

Open Energy Info (EERE)

Urban Transportation Emission Calculator Urban Transportation Emission Calculator Jump to: navigation, search Tool Summary Name: Urban Transportation Emission Calculator Agency/Company /Organization: Transport Canada Sector: Energy Focus Area: Transportation Topics: GHG inventory Resource Type: Software/modeling tools User Interface: Website Website: wwwapps.tc.gc.ca/Prog/2/UTEC-CETU/Menu.aspx?lang=eng Cost: Free References: http://wwwapps.tc.gc.ca/Prog/2/UTEC-CETU/Menu.aspx?lang=eng The Urban Transportation Emissions Calculator (UTEC) is a user-friendly tool for estimating annual emissions from personal, commercial, and public transit vehicles. It estimates greenhouse gas (GHG) and criteria air contaminant (CAC) emissions from the operation of vehicles. It also estimates upstream GHG emissions from the production, refining and

319

What is the GREET Fleet Footprint Calculator  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

GREET Fleet Calculator can estimate petroleum and carbon GREET Fleet Calculator can estimate petroleum and carbon footprints of both on-road vehicles and off-road equipment. What is the GREET Fleet Footprint Calculator? As early adopters of new vehicle technologies, fleets are vital to the success of alternative fuels and advanced vehicles (AFVs). The Greenhouse gases, Regulated Emis- sions, and Energy use in Transportation (GREET) Fleet Foot- print Calculator can help fleets decide on the AFVs that will best help them meet a variety of organizational goals and legal requirements, including reducing their petroleum use and greenhouse gas (GHG) emissions. Currently, the United States imports nearly half of its oil. 1 Because the United States uses about 70% of its oil for transportation, decreasing petroleum consumption in vehicles can substantially

320

Molecular dynamics calculation of free energy  

Science Conference Proceedings (OSTI)

The results of a systematic study of a recently proposed method by Frenkel and Ladd for calculating free energies via molecular dynamics are reported. Internal measures of the error

J. F. Lutsko; D. Wolf; S. Yip

1988-01-01T23:59:59.000Z

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


321

Why first-principles calculations for alloys  

Science Conference Proceedings (OSTI)

A brief non-technical overview of first-principles calculations is presented, with emphasis on prediction of phase equilibria. Merits and drawbacks of various methods are briefly discussed.

de Fontaine, D.

1991-10-01T23:59:59.000Z

322

Why first-principles calculations for alloys?  

Science Conference Proceedings (OSTI)

A brief non-technical overview of first-principles calculations is presented, with emphasis on prediction of phase equilibria. Merits and drawbacks of various methods are briefly discussed.

de Fontaine, D.

1991-10-01T23:59:59.000Z

323

Lumen Maintenance and Light Loss Factors: Consequences of Current Design Practices for LED's  

SciTech Connect

Synopsis: Light loss factors are used to help lighting systems meet quantitative design criteria throughout the life of the installation, but they also influence energy use. As the light sources currently being specified continue to evolve, it is necessary to reevaluate the methods used in calculating light loss factors, as well as carefully consider the consequences of different product performance attributes. Because of the unique operating characteristics of LEDs and lack of a comprehensive lifetime ratingas well as the problematic relationship between lifetime and lumen maintenancedetermining an appropriate lamp lumen depreciation (LLD) factor for LED products is difficult. As a result, a unique solution has been advocated: when quantity of light is an important design consideration, the IES recommends using an LLD of not greater than 0.70. This method deviates from the typical practice for conventional sources of using the ratio of mean to initial lumen output, and can misrepresent actual performance, increase energy use, and inhibit comparisons between products. This paper discusses the complications related to LLD and LEDs, compares the performance of conventional and LED products, and examines alternatives to a maximum LLD of 0.70 for LEDs.

Royer, Michael P.

2013-09-17T23:59:59.000Z

324

Users enlist consultants to calculate costs, savings  

SciTech Connect

Consultants who calculate payback provide expertise and a second opinion to back up energy managers' proposals. They can lower the costs of an energy-management investment by making complex comparisons of systems and recommending the best system for a specific application. Examples of payback calculations include simple payback for a school system, a university, and a Disneyland hotel, as well as internal rate of return for a corporate office building and a chain of clothing stores. (DCK)

1982-05-24T23:59:59.000Z

325

Photon Source Parameters  

NLE Websites -- All DOE Office Websites (Extended Search)

Photon Source Parameters Print Photon Source Parameters Print Summary Graph of Brightness Curves for All Insertion Devices Insertion Device and Bend Magnet Parameters Bend Magnet Superbend Magnet U30 Undulator U50 Undulator U80 Undulator U100 Undulator W114 Wiggler The ALS has six elliptically polarizing undulators, two in straight 4, two in straight 11, and one each in straights 6 and 7. All are arranged with chicanes so that two such devices can be installed to feed two independent beamlines. They can be used in a variety of polarization modes, including circular, elliptical, horizontal, and vertical. These modes can be chosen by appropriate phasing of the magnet rows. The brightness and flux curves below are shown for horizontal and circular polarization. Curves for elliptical and vertical polarization are similar to the horizontal polarization curve, but the minimum photon energy is higher.

326

Overview | Advanced Photon Source  

NLE Websites -- All DOE Office Websites (Extended Search)

APS Overview: APS Overview: Introduction APS Systems Map LINAC Booster Synchrotron Storage Ring Insertion Devices Experiment Hall LOMs & Beamlines Overview of the APS The Advanced Photon Source (APS) at the U.S. Department of Energy's Argonne National Laboratory provides this nation's (in fact, this hemisphere's) brightest storage ring-generated x-ray beams for research in almost all scientific disciplines. Photo: Aerial Photo of APS Aerial photo of the Advanced Photon Source These x-rays allow scientists to pursue new knowledge about the structure and function of materials in the center of the Earth and in outer space, and all points in between. The knowledge gained from this research can impact the evolution of combustion engines and microcircuits, aid in the development of new pharmaceuticals, and pioneer nanotechnologies whose

327

National Synchrotron Light Source  

NLE Websites -- All DOE Office Websites (Extended Search)

Report 2001 Report 2001 National Synchrotron Light Source For the period October 1, 2000 through September 30, 2001 Introduction Science Highlights Year in Review Operations Publications Abstracts Nancye Wright & Lydia Rogers The National Synchrotron Light Source Department is supported by the Office of Basic Energy Sciences United States Department of Energy Washington, D.C. Brookhaven National Laboratory Brookhaven Science Associates, Inc. Upton, New York 11973 Under Contract No. DE-AC02-98CH10886 Mary Anne Corwin Steven N. Ehrlich & Lisa M. Miller Managing Editor Science Editors Production Assistants Cover images (clockwise from top left) 1. from Science Highlight by K.R. Rajashankar, M.R. Chance, S.K. Burley, J. Jiang, S.C. Almo, A. Bresnick, T. Dodatko, R. Huang, G. He,

328

Advanced Photon Source  

NLE Websites -- All DOE Office Websites (Extended Search)

Tomography Interest Group Contact: Robert Winarski, Center for Nanoscale Materials winarski@anl.gov Contact: Francesco De Carlo, Advanced Photon Source decarlo@aps.anl.gov The tomography special interest group of the Advanced Photon Source (APS) at Argonne National Laboratory has been created to promote awareness of the tomography facilities at the APS and to foster communications between the various research groups. Through this group, we believe we can build a strong user community for tomography. The following beamlines have active tomography research programs: 2-BM-B (XOR) http://www.aps.anl.gov/Xray_Science_Division/Xray_Microscopy_and_Imaging/Science_and_Research/Techniques/Tomography/index.html Information about the beamline: http://beam.aps.anl.gov/pls/apsweb/beamline_display_pkg.display_beamline?p_beamline_num_c=31

329

Posters | Advanced Photon Source  

NLE Websites -- All DOE Office Websites (Extended Search)

Your Cart (0 Posters) Your Cart (0 Posters) Your cart is empty. checkout Subtotal: $0.00 update empty Posters Order a printed APS poster! 11 in. x 17 in. prints will be mailed in the order requests are received. 36 in. x 36 in. posters will be sent to school addresses once all orders are processed. The Advanced Photon Source Is The Advanced Photon Source Is Qty: 1 add to cart Technologies from Materials Science Technologies from Materials Science Qty: 1 add to cart Materials Under Extreme Pressure Materials Under Extreme Pressure Qty: 1 add to cart Biological Macromolecules in Action Biological Macromolecules in Action Qty: 1 add to cart Journey to the Center of the Earth Journey to the Center of the Earth Qty: 1 add to cart Earthshaking Monitor Earthshaking Monitor Qty: 1 add to cart Imaging with X-rays

330

Photon Source Parameters  

NLE Websites -- All DOE Office Websites (Extended Search)

Photon Source Parameters Print Photon Source Parameters Print Summary Graph of Brightness Curves for All Insertion Devices Insertion Device and Bend Magnet Parameters Bend Magnet Superbend Magnet U30 Undulator U50 Undulator U80 Undulator U100 Undulator W114 Wiggler The ALS has six elliptically polarizing undulators, two in straight 4, two in straight 11, and one each in straights 6 and 7. All are arranged with chicanes so that two such devices can be installed to feed two independent beamlines. They can be used in a variety of polarization modes, including circular, elliptical, horizontal, and vertical. These modes can be chosen by appropriate phasing of the magnet rows. The brightness and flux curves below are shown for horizontal and circular polarization. Curves for elliptical and vertical polarization are similar to the horizontal polarization curve, but the minimum photon energy is higher.

331

Photon Source Parameters  

NLE Websites -- All DOE Office Websites (Extended Search)

Photon Source Parameters Print Photon Source Parameters Print Summary Graph of Brightness Curves for All Insertion Devices Insertion Device and Bend Magnet Parameters Bend Magnet Superbend Magnet U30 Undulator U50 Undulator U80 Undulator U100 Undulator W114 Wiggler The ALS has six elliptically polarizing undulators, two in straight 4, two in straight 11, and one each in straights 6 and 7. All are arranged with chicanes so that two such devices can be installed to feed two independent beamlines. They can be used in a variety of polarization modes, including circular, elliptical, horizontal, and vertical. These modes can be chosen by appropriate phasing of the magnet rows. The brightness and flux curves below are shown for horizontal and circular polarization. Curves for elliptical and vertical polarization are similar to the horizontal polarization curve, but the minimum photon energy is higher.

332

Photon Source Parameters  

NLE Websites -- All DOE Office Websites (Extended Search)

Photon Source Parameters Print Photon Source Parameters Print Summary Graph of Brightness Curves for All Insertion Devices Insertion Device and Bend Magnet Parameters Bend Magnet Superbend Magnet U30 Undulator U50 Undulator U80 Undulator U100 Undulator W114 Wiggler The ALS has six elliptically polarizing undulators, two in straight 4, two in straight 11, and one each in straights 6 and 7. All are arranged with chicanes so that two such devices can be installed to feed two independent beamlines. They can be used in a variety of polarization modes, including circular, elliptical, horizontal, and vertical. These modes can be chosen by appropriate phasing of the magnet rows. The brightness and flux curves below are shown for horizontal and circular polarization. Curves for elliptical and vertical polarization are similar to the horizontal polarization curve, but the minimum photon energy is higher.

333

Advanced Photon Source  

NLE Websites -- All DOE Office Websites (Extended Search)

0 Advanced Photon Source 0 Advanced Photon Source A U.S. Department of Energy, Office of Science, Office of Basic Energy Sciences national synchrotron x-ray research facility Search Button About Welcome Overview Visiting the APS Mission & Goals Find People Organization Charts Committees Job Openings User Information Prospective Users New Users Current Users APS User Portal Macromolecular Crystallographers Administrators Find a Beamline Apply for Beam Time Contacts Calendars Community Scientific Access Site Access Training Science & Education Science & Research Highlights Conferences Seminars Publications Annual Reports APS Upgrade Courses and Schools Graduate Programs Scientific Software Media Center Calendar of Events APS News User News Argonne/APS Press Releases Argonne/APS Feature Stories Argonne/APS In The News

334

Filtered cathodic arc source  

DOE Patents (OSTI)

Disclosed is a continuous, cathodic arc ion source coupled to a macro-particle filter capable of separation or elimination of macro-particles from the ion flux produced by cathodic arc discharge. The ion source employs an axial magnetic field on a cathode (target) having tapered sides to confine the arc, thereby providing high target material utilization. A bent magnetic field is used to guide the metal ions from the target to the part to be coated. The macro-particle filter consists of two straight solenoids, end to end, but placed at 45{degrees} to one another, which prevents line-of-sight from the arc spot on the target to the parts to be coated, yet provides a path for ions and electrons to flow, and includes a series of baffles for trapping the macro-particles.

Falabella, S.; Sanders, D.M.

1992-12-31T23:59:59.000Z

335

Calibrated vapor generator source  

DOE Patents (OSTI)

A portable vapor generator is disclosed that can provide a controlled source of chemical vapors, such as, narcotic or explosive vapors. This source can be used to test and calibrate various types of vapor detection systems by providing a known amount of vapors to the system. The vapor generator is calibrated using a reference ion mobility spectrometer. A method of providing this vapor is described, as follows: explosive or narcotic is deposited on quartz wool, placed in a chamber that can be heated or cooled (depending on the vapor pressure of the material) to control the concentration of vapors in the reservoir. A controlled flow of air is pulsed over the quartz wool releasing a preset quantity of vapors at the outlet.

Davies, John P. (Idaho Falls, ID); Larson, Ronald A. (Idaho Falls, ID); Goodrich, Lorenzo D. (Shelley, ID); Hall, Harold J. (Idaho Falls, ID); Stoddard, Billy D. (Idaho Falls, ID); Davis, Sean G. (Idaho Falls, ID); Kaser, Timothy G. (Idaho Falls, ID); Conrad, Frank J. (Albuquerque, NM)

1995-01-01T23:59:59.000Z

336

Calibrated vapor generator source  

DOE Patents (OSTI)

A portable vapor generator is disclosed that can provide a controlled source of chemical vapors, such as, narcotic or explosive vapors. This source can be used to test and calibrate various types of vapor detection systems by providing a known amount of vapors to the system. The vapor generator is calibrated using a reference ion mobility spectrometer. A method of providing this vapor is described, as follows: explosive or narcotic is deposited on quartz wool, placed in a chamber that can be heated or cooled (depending on the vapor pressure of the material) to control the concentration of vapors in the reservoir. A controlled flow of air is pulsed over the quartz wool releasing a preset quantity of vapors at the outlet. 10 figs.

Davies, J.P.; Larson, R.A.; Goodrich, L.D.; Hall, H.J.; Stoddard, B.D.; Davis, S.G.; Kaser, T.G.; Conrad, F.J.

1995-09-26T23:59:59.000Z

337

Filtered cathodic arc source  

DOE Patents (OSTI)

A continuous, cathodic arc ion source coupled to a macro-particle filter capable of separation or elimination of macro-particles from the ion flux produced by cathodic arc discharge is described. The ion source employs an axial magnetic field on a cathode (target) having tapered sides to confine the arc, thereby providing high target material utilization. A bent magnetic field is used to guide the metal ions from the target to the part to be coated. The macro-particle filter consists of two straight solenoids, end to end, but placed at 45[degree] to one another, which prevents line-of-sight from the arc spot on the target to the parts to be coated, yet provides a path for ions and electrons to flow, and includes a series of baffles for trapping the macro-particles. 3 figures.

Falabella, S.; Sanders, D.M.

1994-01-18T23:59:59.000Z

338

Open Source Physics  

E-Print Network (OSTI)

Open Source Physics (Brown, 2012; Christian, 2010; Esquembre, 2012; Hwang, 2010) empowers teachers and students to create and use these free tools with the associated intellectual property rights given to customise (Wee & Mak, 2009) the computer models/tools to suit their teaching and learning needs. Open Source Physics (OSP) focuses on design of computer models, such as Easy Java Simulations (EJS) and the use of video modeling and analysis (Tracker). They allow students to investigate, explore and analyse data which is either real or simulated. The OSP approach helps users overcome barriers in creating, using and scaling up meaningful ICT use in education. In Singapore, teachers and students have created or customised existing computer models to design and re-purpose EJS models to suit their context and learning needs. Tracker tools allow students to analyse different aspects of a physics phenomena to deepen their understanding of abstract physics concepts. Using Tracker, students record the motion of ob...

Wee, Loo Kang

2013-01-01T23:59:59.000Z

339

Voltage controlled current source  

DOE Patents (OSTI)

A seven decade, voltage controlled current source is described for use in testing intermediate range nuclear instruments that covers the entire test current range of from 10 picoamperes to 100 microamperes. High accuracy is obtained throughout the entire seven decades of output current with circuitry that includes a coordinated switching scheme responsive to the input signal from a hybrid computer to control the input voltage to an antilog amplifier, and to selectively connect a resistance to the antilog amplifier output to provide a continuous output current source as a function of a preset range of input voltage. An operator controlled switch provides current adjustment for operation in either a real-time simulation test mode or a time response test mode.

Casne, Gregory M. (Pittsburgh, PA)

1992-01-01T23:59:59.000Z

340

Comparisons with Other sources  

U.S. Energy Information Administration (EIA) Indexed Site

Estimates Compared with Other sources Estimates Compared with Other sources The following seven graphs were prepared to give a sense of the variation and confidence level of the EIA-914 estimates. Each graph shows the reported sample production (the starting point for making an estimate), the EIA-914 estimates, State reported data, HPDI reported data, and Lippman Consulting data for comparison. State data are obtained directly from the States usually via a State agency web site as a monthly total. HPDI is a commercial data vender. They acquire data from all the States and provide it to EIA in a single format and query system at the well or lease level. EIA then sums this data to the operator level and State level. HPDI data typically lag the State data by 1 or 2 months.

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


341

HYDRAULIC CALCULATIONS FOR A MODIFIED IN-SITU RETORT  

E-Print Network (OSTI)

LBL-1 0431 UC-91 HYDRAULIC CALCULATIONS FOR A MODIFIED IN-REFERENCES . . , . HYDRAULIC CALCULATIONS FOR ACalifomia. LBL-10431 HYDRAULIC CALCULATIONS FOR A MODIFIED

Hall, W.G.

2012-01-01T23:59:59.000Z

342

Tool and Calculator (Transit, Fuel) | Open Energy Information  

Open Energy Info (EERE)

This webside provide Tools & Calculators like Public Transit In Your Community, Fuel Saving Calculator, Carbon saving calculator, Transit Savings Report and transit benefits...

343

High current ion source  

DOE Patents (OSTI)

An ion source utilizing a cathode and anode for producing an electric arc therebetween. The arc is sufficient to vaporize a portion of the cathode to form a plasma. The plasma leaves the generation region and expands through another regon. The density profile of the plasma may be flattened using a magnetic field formed within a vacuum chamber. Ions are extracted from the plasma to produce a high current broad on beam.

Brown, Ian G. (1088 Woodside Rd., Berkeley, CA 94708); MacGill, Robert A. (645 Kern St., Richmond, CA 94805); Galvin, James E. (2 Commodore Dr. #276, Emeryville, CA 94608)

1990-01-01T23:59:59.000Z

344

Compact superradiant Cerenkov source  

Science Conference Proceedings (OSTI)

An economical, coherent, and widely tunable source does not exist spanning the far-infrared electromagnetic spectral range of 50-1000 {mu}m in wavelength. The Cerenkov free-electron laser (CFEL) is a promising candidate. This report describes an experimental investigation of a compact CFEL driven by a high-quality low-energy electron beam. Cerenkov emission and strong gain but remarkably low output coupling were observed.

Owens, I.J.; Brownell, J.H. [Department of Physics and Astronomy, Dartmouth College, Hanover, New Hampshire 03755-3528 (United States)

2005-05-15T23:59:59.000Z

345

FABRICATION OF NEUTRON SOURCES  

DOE Patents (OSTI)

A method is presented for preparing a more efficient neutron source comprising inserting in a container a quantity of Po-210, inserting B powder coated with either Ag, Pt, or Ni. The container is sealed and then slowly heated to about 450 C to volatilize the Po and effect combination of the coated powder with the Po. The neutron flux emitted by the unit is moritored and the heating step is terminated when the flux reaches a maximum or selected level.

Birden, J.H.

1959-01-20T23:59:59.000Z

346

Negative ion source  

DOE Patents (OSTI)

A method and apparatus for providing a negative ion source accelerates electrons away from a hot filament electron emitter into a region of crossed electric and magnetic fields arranged in a magnetron configuration. During a portion of the resulting cycloidal path, the electron velocity is reduced below its initial value. The electron accelerates as it leaves the surface at a rate of only slightly less than if there were no magnetic field, thereby preventing a charge buildup at the surface of the emitter. As the electron traverses the cycloid, it is decelerated during the second, third, and fourth quadrants, then reeccelerated as it approaches the end of the fourth quadrant to regain its original velocity. The minimum velocity occurs during the fourth quadrant, and corresponds to an electron temperature of 200.degree. to 500.degree. for the electric and magnetic fields commonly encountered in the ion sources of magnetic sector mass spectrometers. An ion source using the above-described thermalized electrons is also disclosed.

Delmore, James E. (Idaho Falls, ID)

1987-01-01T23:59:59.000Z

347

Open-Source GIS  

SciTech Connect

The components making up an Open Source GIS are explained in this chapter. A map server (Sect. 30.1) can broadly be defined as a software platform for dynamically generating spatially referenced digital map products. The University of Minnesota MapServer (UMN Map Server) is one such system. Its basic features are visualization, overlay, and query. Section 30.2 names and explains many of the geospatial open source libraries, such as GDAL and OGR. The other libraries are FDO, JTS, GEOS, JCS, MetaCRS, and GPSBabel. The application examples include derived GIS-software and data format conversions. Quantum GIS, its origin and its applications explained in detail in Sect. 30.3. The features include a rich GUI, attribute tables, vector symbols, labeling, editing functions, projections, georeferencing, GPS support, analysis, and Web Map Server functionality. Future developments will address mobile applications, 3-D, and multithreading. The origins of PostgreSQL are outlined and PostGIS discussed in detail in Sect. 30.4. It extends PostgreSQL by implementing the Simple Feature standard. Section 30.5 details the most important open source licenses such as the GPL, the LGPL, the MIT License, and the BSD License, as well as the role of the Creative Commons.

Vatsavai, Raju [ORNL; Burk, Thomas E [University of Minnesota; Lime, Steve [Minnesota Department of Natural Resources

2012-01-01T23:59:59.000Z

348

Improved negative ion source  

DOE Patents (OSTI)

A method and apparatus for providing a negative ion source accelerates electrons away from a hot filament electron emitter into a region of crossed electric and magnetic fields arranged in a magnetron configuration. During a portion of the resulting cycloidal path, the electron velocity is reduced below its initial value. The electron accelerates as it leaves the surface at a rate of only slightly less than if there were no magnetic field, thereby preventing a charge buildup at the surface of the emitter. As the electron traverses the cycloid, it is decelerated during the second, third, and fourth quadrants, then reaccelerated as it approaches the end of the fourth quadrant to regain its original velocity. The minimum velocity occurs during the fourth quadrant, and corresponds to an electron temperature of 200 to 500/sup 0/C for the electric and magnetic fields commonly encountered in the ion sources of magnetic sector mass spectrometers. An ion source using the above-described thermalized electrons is also disclosed.

Delmore, J.E.

1984-05-01T23:59:59.000Z

349

IV Estimation of Panels with Factor Residuals  

E-Print Network (OSTI)

. In microeconometric panels, the factor structure may capture different sources of unobserved individual-specific heterogeneity, the impact of which varies intertem- porally in an arbitrary way. For instance, in studies of production functions, the factor loadings may... supply, Euler equations for household consumption, and em- pirical growth models. In these models the coefficient of the lagged dependent variable captures inertia, habit formation and costs of adjustment and therefore it has structural significance (see...

Robertson, Donald; Sara dis, Vasilis

2013-06-04T23:59:59.000Z

350

Anthrax Lethal Factor  

NLE Websites -- All DOE Office Websites (Extended Search)

Thiang Yian Wong, Robert Schwarzenbacher and Robert C. Liddington Thiang Yian Wong, Robert Schwarzenbacher and Robert C. Liddington The Burnham Institute, 10901 North Torrey Pines Road, La Jolla, CA 92037. Anthrax Toxin is a major virulence factor in the infectious disease, Anthrax1. This toxin is produced by Bacillus anthracis, which is an encapsulated, spore-forming, rod-shaped bacterium. Inhalation anthrax, the most deadly form, is contracted through breathing spores. Once spores germinate within cells of the immune system called macrophages2, bacterial cells are released into the bloodstream. There they proliferate rapidly and secrete Anthrax Toxin, ultimately leading to septic shock and death. Although antibiotics may be used to kill the bacteria, the level of toxin has often become so high in the bloodstream that removing the bacteria alone is not sufficient to prevent death. Therefore, the design of anti-toxins offers the prospect of treatment in the advanced stages of infection. Together with collaborators from the NIH and Harvard Medical School, we are involved in the atomic resolution study of the Anthrax Toxin components and their complexes, including small molecules with therapeutic potential. Data collection at SSRL and other synchrotron radiation sources has been key to the advances made in this research so far and is expected to play a continuing role in the future.

351

Application of the adjoint method in atmospheric radiative transfer calculations  

DOE Green Energy (OSTI)

The transfer of solar radiation through a standard mid-latitude summer atmosphere including different amounts of aerosols (from clear to hazy) has been computed. The discrete-ordinates (S/sub N/) method, which has been developed to a high degree of computational efficiency and accuracy primarily for nuclear radiation shielding applications, is employed in a forward as well as adjoint mode. In the adjoint mode the result of a transfer calculation is an importance function (adjoint intensity) which allows the calculation of transmitted fluxes, or other radiative responses, for any arbitrary source distribution. The theory of the adjoint method is outlined in detail and physical interpretations are developed for the adjoint intensity. If, for example, the downward directed solar flux at ground level, F/sub lambda/ (z = 0), is desired for N different solar zenith angles, a regular (forward) radiative transfer calculation must be repeated for each solar zenith angle. In contrast, only 1 adjoint transfer calculation gives F/sub lambda/ (z = 0) for all solar zenith angles in a hazy aerosol atmosphere, for 1 wavelength interval, in 2.3 seconds on a CDC-7600 computer. A total of 155 altitude zones were employed between 0 and 70 km, and the convergence criterion for the ratio of fluxes from successive iterations was set at 2 x 10/sup -3/. Our results demonstrate not only the applicability of the highly efficient modern S/sub N/ codes, but indicate also conceptual and computational advantages when the adjoint formulation of the radiative transfer equation is used.

Gerstl, S.A.W.

1979-01-01T23:59:59.000Z

352

Individual Dose Calculations with Use of the Revised Techa River Dosimetry System TRDS-2009D  

SciTech Connect

An updated deterministic version of the Techa River Dosimetry System (TRDS-2009D) has been developed to estimate individual doses from external exposure and intake of radionuclides for residents living on the Techa River contaminated as a result of radioactive releases from the Mayak plutonium facility in 19491956. The TRDS-2009D is designed as a flexible system that uses, depending on the input data for an individual, various elements of system databases to provide the dosimetric variables requested by the user. Several phases are included in the computation schedule. The first phase includes calculations with use of a common protocol for all cohort members based on village-average-intake functions and external dose rates; individual data on age, gender and history of residence are included in the first phase. This phase results in dose estimates similar to those obtained with system TRDS-2000 used previously to derive risks of health effects in the Techa River Cohort. The second phase includes refinement of individual internal doses for those persons who have had body-burden measurements or exposure parameters specific to the household where he/she lived on the Techa River. The third phase includes summation of individual doses from environmental exposure and from radiological examinations. The results of TRDS-2009D dose calculations have demonstrated for the ETRC members on average a moderate increase in RBM dose estimates (34%) and a minor increase (5%) in estimates of stomach dose. The calculations for the members of the ETROC indicated similar small changes for stomach, but significant increase in RBM doses (400%). Individual-dose assessments performed with use of TRDS-2009D have been provided to epidemiologists for exploratory risk analysis in the ETRC and ETROC. These data provide an opportunity to evaluate the possible impact on radiogenic risk of such factors as confounding exposure (environmental and medical), changes in the Techa River source-term data and the change of the approach to individual internal dose estimation (90Sr-body burden measurements and family correlations vs. village averages). Our further plan is to upgrade the TRDS-2009D and to complete a stochastic version of the dosimetry system.

Degteva, M. O.; Shagina, N. B.; Tolstykh, E. I.; Vorobiova, M. I.; Anspaugh, L. R.; Napier, Bruce A.

2009-10-23T23:59:59.000Z

353

Impact of the 235U Covariance Data in Benchmark Calculations  

SciTech Connect

The error estimation for calculated quantities relies on nuclear data uncertainty information available in the basic nuclear data libraries such as the U.S. Evaluated Nuclear Data File (ENDF/B). The uncertainty files (covariance matrices) in the ENDF/B library are generally obtained from analysis of experimental data. In the resonance region, the computer code SAMMY is used for analyses of experimental data and generation of resonance parameters. In addition to resonance parameters evaluation, SAMMY also generates resonance parameter covariance matrices (RPCM). SAMMY uses the generalized least-squares formalism (Bayes method) together with the resonance formalism (R-matrix theory) for analysis of experimental data. Two approaches are available for creation of resonance-parameter covariance data. (1) During the data-evaluation process, SAMMY generates both a set of resonance parameters that fit the experimental data and the associated resonance-parameter covariance matrix. (2) For existing resonance-parameter evaluations for which no resonance-parameter covariance data are available, SAMMY can retroactively create a resonance-parameter covariance matrix. The retroactive method was used to generate covariance data for 235U. The resulting 235U covariance matrix was then used as input to the PUFF-IV code, which processed the covariance data into multigroup form, and to the TSUNAMI code, which calculated the uncertainty in the multiplication factor due to uncertainty in the experimental cross sections. The objective of this work is to demonstrate the use of the 235U covariance data in calculations of critical benchmark systems.

Leal, Luiz C [ORNL; Mueller, Don [ORNL; Arbanas, Goran [ORNL; Wiarda, Dorothea [ORNL; Derrien, Herve [ORNL

2008-01-01T23:59:59.000Z

354

Calculated K-effectives using ENDF/B-V data for U + Pu solution critical experiments  

DOE Green Energy (OSTI)

Effective multiplication factors for 12 critical experiments have been calculated using multigroup cross sections derived from the ENDF/B-V library. All 12 experiments contained mixed plutonium and uranium nitrate solutions. The range of hydrogen-to-fissile plutonium atom ratios spanned by these experiments was 200 to 2200. A comparison with K-effectives calculated with ENDF/B-IV data is presented.

Primm, R.T. III; Mincey, J.F.

1981-01-01T23:59:59.000Z

355

Calculation of pressure waves in substation buildings due to arcing faults  

SciTech Connect

Pressure stress from internal arcing includes static and dynamic phenomena. These phenomena can be distinguished with the help of the pulsation factor. The ray tracing technique presented allows the three-dimensional calculation of pressure stresses including transient effects. Two examples demonstrating the importance of pressure waves on the stress of rooms are presented. A calculation procedure is given which enables an improvement of the design of substation buildings.

Dasbach, A.; Pietsch, G.J. (Grundegebiete der Elektrotechnik und Gasentladungstechnik, Aachen Univ. of Technology, Aachen (DE))

1990-10-01T23:59:59.000Z

356

(beta beta)_{0 nu}-decay: a possible test of the nuclear matrix element calculations  

E-Print Network (OSTI)

The existing calculations of the nuclear matrix elements of the neutrinoless double beta-decay differ by about a factor three. This uncertainty prevents quantative interpretation of the results of experiments searching for this process. We suggest here that the observation of the neutrinoless double beta-decay of several nuclei in future experiments of could allow to test different calculations of the nuclear matrix elements through the direct comparison of them with the experimental data.

S. M. Bilenky; J. A. Grifols

2002-07-23T23:59:59.000Z

357

Performance Calculations of APPLE II Undulator  

NLE Websites -- All DOE Office Websites (Extended Search)

Advanced Photon Source (formerly MD-TN-2008-001) R. Dejus - MD GroupASD S. Sasaki - Hiroshima Synchrotron Radiation Center, Higashi-Hiroshima, 739-0046, Japan Rev. 3, November...

358

Conversion factors for energy equivalents: All factors  

Science Conference Proceedings (OSTI)

... Previous page of energy equivalents. Definition of uncertainty notation eg, 123(45) | Basis of conversion factors for energy equivalents. Top. ...

359

PABS: A Computer Program to Normalize Emission Probabilities and Calculate Realistic Uncertainties  

SciTech Connect

The program PABS normalizes relative particle emission probabilities to an absolute scale and calculates the relevant uncertainties on this scale. The program is written in Java using the JDK 1.6 library. For additional information about system requirements, the code itself, and compiling from source, see the README file distributed with this program. The mathematical procedures used are given below.

Caron, D. S.; Browne, E.; Norman, E. B.

2009-08-21T23:59:59.000Z

360

National Synchrotron Light Source  

NLE Websites -- All DOE Office Websites (Extended Search)

49 49 Hand Safety Date: January 7, 2011 Editor: Lori Stiegler It's not unusual for experiment needs to change, and beam time to be limited while conducting research at the NSLS. Unfortunately, these factors, and several other contributing factors, converged recently and adversely affected an experimenter. The result was a hand injury that required a trip to the hospital, and sutures. In the case of this injury, the user was trying to fashion a new sample holder because of difficulty with the equipment he had brought from his home institution. The idea for the substitute sample holder had been previously discussed with his work group, but never tried. Using the alternate tools and holders he had brought, he tried to cut a slot out of a hard plastic tube with a razor

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361

Source options for nuclear weapons identification system  

Science Conference Proceedings (OSTI)

This report briefly presents the advantages and disadvantages of two timed sources of neutrons that can be used with the source-driven noise analysis method: (1) {sup 252}Cf in an ionization chamber and (2) an associated-particle sealed tube neutron generator (APSTNG). These sources can be used with frequency and time analysis methods for nuclear weapons identification, quality assurance in production, special nuclear materials assay, criticality safety, and provision of measured data for verification of neutron and gamma ray transport calculational methods. The advantages of {sup 252}Cf for a nuclear materials identification system are that it is simple, reliable, and small and that all source events are detected. The disadvantages are that it cannot be turned off, leads to small radiation doses in handling, and produces more than one neutron per fission event. The advantages of APSTNG are that it is directional, can be turned off, and has one particle per deuterium-tritium reaction. The disadvantages are that it is large and complicated compared to {sup 252}Cf.

Mihalczo, J.T.; Koehler, P.E.; Valentine, T.E.; Phillips, L.D.

1995-07-01T23:59:59.000Z

362

DRY TRANSFER FACILITY CRITICALITY SAFETY CALCULATIONS  

SciTech Connect

This design calculation updates the previous criticality evaluation for the fuel handling, transfer, and staging operations to be performed in the Dry Transfer Facility (DTF) including the remediation area. The purpose of the calculation is to demonstrate that operations performed in the DTF and RF meet the nuclear criticality safety design criteria specified in the ''Project Design Criteria (PDC) Document'' (BSC 2004 [DIRS 171599], Section 4.9.2.2), the nuclear facility safety requirement in ''Project Requirements Document'' (Canori and Leitner 2003 [DIRS 166275], p. 4-206), the functional/operational nuclear safety requirement in the ''Project Functional and Operational Requirements'' document (Curry 2004 [DIRS 170557], p. 75), and the functional nuclear criticality safety requirements described in the ''Dry Transfer Facility Description Document'' (BSC 2005 [DIRS 173737], p. 3-8). A description of the changes is as follows: (1) Update the supporting calculations for the various Category 1 and 2 event sequences as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2005 [DIRS 171429], Section 7). (2) Update the criticality safety calculations for the DTF staging racks and the remediation pool to reflect the current design. This design calculation focuses on commercial spent nuclear fuel (SNF) assemblies, i.e., pressurized water reactor (PWR) and boiling water reactor (BWR) SNF. U.S. Department of Energy (DOE) Environmental Management (EM) owned SNF is evaluated in depth in the ''Canister Handling Facility Criticality Safety Calculations'' (BSC 2005 [DIRS 173284]) and is also applicable to DTF operations. Further, the design and safety analyses of the naval SNF canisters are the responsibility of the U.S. Department of the Navy (Naval Nuclear Propulsion Program) and will not be included in this document. Also, note that the results for the Monitored Geologic Repository (MGR) Site specific Cask (MSC) calculations are limited to the specific design chosen (see Assumption 3.4). A more current design will be included in the next revision of the criticality calculations for the Aging Facility. In addition, this calculation is valid for the current design as provided in Attachment III of the DTF and may not reflect the ongoing design evolution of the facility. However, it is anticipated that design changes to the facility layout will have little or no impact on the criticality results and/or conclusions presented in this document.

C.E. Sanders

2005-05-17T23:59:59.000Z

363

Calculated /alpha/-induced thick target neutron yields and spectra, with comparison to measured data  

Science Conference Proceedings (OSTI)

One component of the neutron source associated with the decay of actinide nuclides in many environments is due to the interaction of decay /alpha/ particles in (/alpha/,n) reactions on low Z nuclides. Measurements of (/alpha/,n) thick target neutron yields and associated neutron spectra have been made for only a few combinations of /alpha/ energy and target nuclide or mixtures of actinide and target nuclides. Calculations of thick target neutron yields and spectra with the SOURCES code require /alpha/-energy-dependent cross sections for (/alpha/,n) reactions, as well as branching fractions leading to the energetically possible levels of the product nuclides. A library of these data has been accumulated for target nuclides of Z /le/ 15 using that available from measurements and from recent GNASH code calculations. SOURCES, assuming neutrons to be emitted isotopically in the center-of-mass system, uses libraries of /alpha/ stopping cross sections, (/alpha/,n) reaction cross reactions, product nuclide level branching fractions, and actinide decay /alpha/ spectra to calculate thick target (/alpha/,n) yields and neutron spectra for homogeneous combinations of nuclides. The code also calculates the thick target yield and angle intergrated neutron spectrum produced by /alpha/-particle beams on targets of homogeneous mixtures of nuclides. Illustrative calculated results are given and comparisons are made with measured thick target yields and spectra. 50 refs., 1 fig., 2 tabs.

Wilson, W.B.; Bozoian, M.; Perry, R.T.

1988-01-01T23:59:59.000Z

364

Sources of tritium  

SciTech Connect

A review of tritium sources is presented. The tritium production and release rates are discussed for light water reactors (LWRs), heavy water reactors (HWRs), high temperature gas cooled reactors (HTGRs), liquid metal fast breeder reactors (LMFBRs), and molten salt breeder reactors (MSBRs). In addition, release rates are discussed for tritium production facilities, fuel reprocessing plants, weapons detonations, and fusion reactors. A discussion of the chemical form of the release is included. The energy producing facilities are ranked in order of increasing tritium production and release. The ranking is: HTGRs, LWRs, LMFBRs, MSBRs, and HWRs. The majority of tritium has been released in the form of tritiated water.

Phillips, J.E.; Easterly, C.E.

1980-12-01T23:59:59.000Z

365

The possible test of the calculations of nuclear matrix elements of the $(??)_{0?}$-decay  

E-Print Network (OSTI)

The existing calculations of the nuclear matrix elements of the neutrinoless double $\\beta$-decay differ by about a factor three. This uncertainty prevents quantitative interpretation of the results of experiments searching for this process. We suggest here that the observation of the neutrinoless double $\\beta$-decay of {\\em several} nuclei could allow to test calculations of the nuclear matrix elements through the comparison of the ratios of the calculated lifetimes with experimental data. It is shown that the ratio of the lifetimes is very sensitive to different models.

S. M. Bilenky; J. A. Grifols

2002-11-07T23:59:59.000Z

366

Calculated Influence of Temperature-Related Factors on Ozone Formation Rates in the Lower Troposphere  

Science Conference Proceedings (OSTI)

Using an atmospheric chemical reaction mechanism applied to air parcels near the earth's surface, the sensitivities ozone (O3) formation rates are quantified for changes in four meteorologically controlled parameters: temperature, sunlight ...

Chris J. Walcek; Hong-H. Yuan

1995-05-01T23:59:59.000Z

367

Energy Savings Calculator for Air-Cooled Electric Chillers | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Energy Savings Calculator for Air-Cooled Electric Chillers Energy Savings Calculator for Air-Cooled Electric Chillers Energy Savings Calculator for Air-Cooled Electric Chillers January 16, 2014 - 4:19pm Addthis This cost calculator is a screening tool that estimates a product's lifetime energy cost savings at various efficiency levels. Learn more about the calculator assumptions and definitions. Project Type Is this a new installation or a replacement? New Replacement How many chillers will you purchase? Performance Factors Existing What is the existing design condition? Full Load Partial Load What is the cooling capacity of the existing chiller? tons What is the full-load efficiency of the existing chiller? EER What is the partial-load efficiency of the existing chiller? EER New What is the new design condition? Full Load Partial Load

368

Computationally efficient implementation of combustion chemistry in parallel PDF calculations  

SciTech Connect

In parallel calculations of combustion processes with realistic chemistry, the serial in situ adaptive tabulation (ISAT) algorithm [S.B. Pope, Computationally efficient implementation of combustion chemistry using in situ adaptive tabulation, Combustion Theory and Modelling, 1 (1997) 41-63; L. Lu, S.B. Pope, An improved algorithm for in situ adaptive tabulation, Journal of Computational Physics 228 (2009) 361-386] substantially speeds up the chemistry calculations on each processor. To improve the parallel efficiency of large ensembles of such calculations in parallel computations, in this work, the ISAT algorithm is extended to the multi-processor environment, with the aim of minimizing the wall clock time required for the whole ensemble. Parallel ISAT strategies are developed by combining the existing serial ISAT algorithm with different distribution strategies, namely purely local processing (PLP), uniformly random distribution (URAN), and preferential distribution (PREF). The distribution strategies enable the queued load redistribution of chemistry calculations among processors using message passing. They are implemented in the software x2f{sub m}pi, which is a Fortran 95 library for facilitating many parallel evaluations of a general vector function. The relative performance of the parallel ISAT strategies is investigated in different computational regimes via the PDF calculations of multiple partially stirred reactors burning methane/air mixtures. The results show that the performance of ISAT with a fixed distribution strategy strongly depends on certain computational regimes, based on how much memory is available and how much overlap exists between tabulated information on different processors. No one fixed strategy consistently achieves good performance in all the regimes. Therefore, an adaptive distribution strategy, which blends PLP, URAN and PREF, is devised and implemented. It yields consistently good performance in all regimes. In the adaptive parallel ISAT strategy, the type and extent of redistribution is determined 'on the fly' based on the prediction of future simulation time. Compared to the PLP/ISAT strategy where chemistry calculations are essentially serial, a speed-up factor of up to 30 is achieved. The study also demonstrates that the adaptive strategy has acceptable parallel scalability.

Lu Liuyan [Sibley School of Mechanical and Aerospace Engineering, Cornell University, Upson Hall 245, Ithaca, NY 14853 (United States)], E-mail: lu.liuyan@gmail.com; Lantz, Steven R. [Center for Advanced Computing, Cornell University, Ithaca, NY 14853 (United States); Ren Zhuyin; Pope, Stephen B. [Sibley School of Mechanical and Aerospace Engineering, Cornell University, Upson Hall 245, Ithaca, NY 14853 (United States)

2009-08-20T23:59:59.000Z

369

Building Technologies Office: 179D DOE Calculator  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

179D DOE Calculator 179D DOE Calculator EERE » Building Technologies Office » 179D DOE Calculator Printable Version Bookmark and Share What is the 179D federal tax deduction? Section 179D of the Federal Tax Code provides a tax deduction for energy efficiency improvements to commercial buildings. A building may qualify for a tax deduction under Section 179D not to exceed $1.80/ft² for whole building performance or $0.60/ft² for a partially qualifying property for envelope, heating, ventilating, and air conditioning (HVAC), or lighting improvements. In addition, a building may qualify with a reduced installed lighting power under the interim lighting rule. Energy simulations are required to show compliance with the energy and power cost savings requirements. View more detailed information.

370

Eddy-Current-Induced Multipole Field Calculations  

NLE Websites -- All DOE Office Websites (Extended Search)

Eddy-Current-Induced Multipole Field Calculations Eddy-Current-Induced Multipole Field Calculations September 29, 2003 1 Eddy-Current-Induced Multipole Field Calculations Nicholas S. Sereno, Suk H. Kim 1.0 Abstract Time-varying magnetic fields of magnets in booster accelerators induce substantial eddy currents in the vacuum chambers. The eddy currents in turn act to produce various multi- pole fields that act on the beam. These fields must be taken into account when doing a lat- tice design. In the APS booster, the relatively long dipole magnets (3 meters) are linearly ramped to accelerate the injected 325 MeV beam to 7 GeV. Substantial dipole and sextu- pole fields are generated in the elliptical vacuum chamber from the induced eddy currents. In this note, formulas for the induced dipole and sextupole fields are derived for elliptical and rectangular vacuum chambers for a time-varying dipole field. A discussion is given

371

Improved Calculation of Thermal Fission Energy  

E-Print Network (OSTI)

Thermal fission energy is one of the basic parameters needed in the calculation of antineutrino flux for reactor neutrino experiments. It is useful to improve the precision of the thermal fission energy calculation for current and future reactor neutrino experiments, which are aimed at more precise determination of neutrino oscillation parameters. In this article, we give new values for thermal fission energies of some common thermal reactor fuel iso-topes, with improvements on two aspects. One is more recent input data acquired from updated nuclear databases. The other, which is unprecedented, is a consideration of the production yields of fission fragments from both thermal and fast incident neutrons for each of the four main fuel isotopes. The change in calculated antineutrino flux due to the new values of thermal fission energy is about 0.33%, and the uncertainties of the new values are about 30% smaller.

Ma, X B; Wang, L Z; Chen, Y X; Cao, J

2013-01-01T23:59:59.000Z

372

Computerized Energy and Treatment Cost Calculations  

E-Print Network (OSTI)

A computer program has been developed that quickly calculates blowdown heat loss as a function of makeup water, boiler water chemistry, and blowdown recovery equipment. By inputting water analysis, basic system parameters, and type of fuel, the cost of heat loss in the blowdown can be quickly and accurately determined. Present operating systems can quickly be evaluated as to potential cost savings on the addition of a blowdown flash tank and/or a recovery heat exchanger. Proposed systems can be engineered from the start with an eye to decreasing energy loss and saving money. In addition, the proper internal treatment is recommended along with appropriate products. Cost of energy lost in the blowdown is calculated based on different levels of blowdown heat recovery. Accurate calculations are readily available to make more intelligent decisions on the purchase of recovery equipment, rather than depending on very tedious, potentially inaccurate determinations by long hand.

Trace, W. L.

1981-01-01T23:59:59.000Z

373

Healthcare Energy Impact Calculator | Open Energy Information  

Open Energy Info (EERE)

Healthcare Energy Impact Calculator Healthcare Energy Impact Calculator Jump to: navigation, search Tool Summary Name: Healthcare Energy Impact Calculator Agency/Company /Organization: Practice Greenhealth Sector: Climate User Interface: Website Complexity/Ease of Use: Simple Website: www.eichealth.org/ Cost: Free Related Tools UNEP-Bioenergy Decision Support Tool Global Relationship Assessment to Protect the Environment (GRAPE) World Induced Technical Change Hybrid (WITCH) ... further results Find Another Tool FIND DEVELOPMENT IMPACTS ASSESSMENT TOOLS An online tool based on U.S. Environmental Protection Agency (EPA) analysis of health impacts of power plant emissions of sulfur dioxide, nitrogen oxides, and mercury, this tool estimates premature deaths, chronic bronchitis, asthma attacks, emergency room visits, and more, by kWh/year.

374

Emission Factors (EMFAC) | Open Energy Information  

Open Energy Info (EERE)

Emission Factors (EMFAC) Emission Factors (EMFAC) Jump to: navigation, search Tool Summary LAUNCH TOOL Name: EMFAC Agency/Company /Organization: California Environmental Protection Agency Sector: Energy Focus Area: Transportation Phase: Determine Baseline Topics: Baseline projection, GHG inventory Resource Type: Software/modeling tools, Online calculator User Interface: Spreadsheet Website: www.arb.ca.gov/msei/onroad/latest_version.htm Country: United States Cost: Free Northern America References: http://www.arb.ca.gov/msei/onroad/latest_version.htm The EMission FACtors (EMFAC) model is used to calculate emission rates from all motor vehicles, such as passenger cars to heavy-duty trucks, operating on highways, freeways and local roads in California. EMFAC2007 is the most recent version of this model.

375

Paramagnetic form factors from itinerant electron theory  

Science Conference Proceedings (OSTI)

Elastic neutron scattering experiments performed over the past two decades have provided accurate information about the magnetic form factors of paramagnetic transition metals. These measurements have traditionally been analyzed in terms of an atomic-like theory. There are, however, some cases where this procedure does not work, and there remains the overall conceptual problem of using an atomistic theory for systems where the unpaired-spin electrons are itinerant. We have recently developed computer codes for efficiently evaluating the induced magnetic form factors of fcc and bcc itinerant electron paramagnets. Results for the orbital and spin contributions have been obtained for Cr, Nb, V, Mo, Pd and Rh based on local density bands. By using calculated spin enhancement parameters, we find reasonable agreement between theory and neutron form factor data. In addition, these zero parameter calculations yield predictions for the bulk susceptibility on an absolute scale which are in reasonable agreement with experiment in all treated cases except palladium.

Cooke, J.F.; Liu, S.H.; Liu, A.J.

1984-09-01T23:59:59.000Z

376

SOURCE TERMS IN THE TRANSIENT SEEPAGE EQUATION  

E-Print Network (OSTI)

Equation; Pore Pressure Generation; Sources; Source Terms)In this paper, sources involving the generation of mass areincludes source terms for both fluid mass generation and

Narasimhan, T.N.

2013-01-01T23:59:59.000Z

377

Radiological Dose Calculations for Fusion Facilities  

Science Conference Proceedings (OSTI)

This report summarizes the results and rationale for radiological dose calculations for the maximally exposed individual during fusion accident conditions. Early doses per unit activity (Sieverts per TeraBecquerel) are given for 535 magnetic fusion isotopes of interest for several release scenarios. These data can be used for accident assessment calculations to determine if the accident consequences exceed Nuclear Regulatory Commission and Department of Energy evaluation guides. A generalized yearly dose estimate for routine releases, based on 1 Terabecquerel unit releases per radionuclide, has also been performed using averaged site parameters and assumed populations. These routine release data are useful for assessing designs against US Environmental Protection Agency yearly release limits.

Michael L. Abbott; Lee C. Cadwallader; David A. Petti

2003-04-01T23:59:59.000Z

378

Statistical Uncertainty Analysis Applied to Criticality Calculation  

Science Conference Proceedings (OSTI)

In this paper, we present an uncertainty methodology based on a statistical approach, for assessing uncertainties in criticality prediction using monte carlo method due to uncertainties in the isotopic composition of the fuel. The methodology has been applied to criticality calculations with MCNP5 with additional stochastic input of the isotopic fuel composition. The stochastic input were generated using the latin hypercube sampling method based one the probability density function of each nuclide composition. The automatic passing of the stochastic input to the MCNP and the repeated criticality calculation is made possible by using a python script to link the MCNP and our latin hypercube sampling code.

Hartini, Entin; Andiwijayakusuma, Dinan; Susmikanti, Mike; Nursinta, A. W. [Centre for Nuclear Informatics Development, National Nuclear Energy Agency of Indonesia (Indonesia)

2010-06-22T23:59:59.000Z

379

Energy Cost Calculator for Commercial Heat Pumps (5.4 >=< 20 Tons) |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Heat Pumps (5.4 >=< 20 Tons) Heat Pumps (5.4 >=< 20 Tons) Energy Cost Calculator for Commercial Heat Pumps (5.4 >=< 20 Tons) October 8, 2013 - 2:22pm Addthis Vary equipment size, energy cost, hours of operation, and /or efficiency level. INPUT SECTION Input the following data (if any parameter is missing, calculator will set to default value). Defaults Project Type New Installation Replacement New Installation Condenser Type Air Source Water Source Air Source Existing Capacity * ton - Existing Cooling Efficiency * EER - Existing Heating Efficiency * COP - Existing IPLV Efficiency * IPLV - New Capacity ton 10 tons New Cooling Efficiency EER 10.1 EER New Heating Efficiency COP 3.2 COP New IPLV Efficiency IPLV 10.4 IPLV Energy Cost $ per kWh $0.06 per kWh

380

Kinematics of Compton backscattering x-ray source for angiography  

SciTech Connect

Calculations of X-Ray production rates, energy spread, and spectrum of Compton-backscattered photons from a Free Electron Laser on an electron beam in a low energy (136-MeV) compact (8.5-m circumference) storage ring indicate that an X-Ray intensity of 34.6 10{sup 7} X-Ray photons per 0.5-mm {times} 0.5-mm pixel for Coronary Angiography near the 33.169-keV iodine K-absorption edge can be achieved in a 4-msec pulse within a scattering cone of 1-mrad half angle. This intensity, at 10-m from the photon-electron interaction point to the patient is about a factor of 10 larger than presently achieved from a 4.5-T superconducting wiggler source in the NSLS 2.5-GeV storage ring and over an area about 5 times larger. The 2.2-keV energy spread of the Compton-backscattered beam is, however, much larger than the 70-eV spread presently attained form the wiggler source and use of a monochromator. The beam spot at the 10-m interaction point-to-patient distance is 20-mm diameter; larger spots are attainable at larger distances but with a corresponding reduction in X-Ray flux. Such a facility could be an inexpensive clinical alternative to present methods of non-invasive Digital Subtraction Angiography (DSA), small enough to be deployed in an urban medical center, and could have other medical, industrial and aerospace applications. Problems with the Compton backscattering source include laser beam heating of the mirror in the FEL oscillator optical cavity, achieving a large enough X-Ray beam spot at the patient, and obtaining radiation damping of the transverse oscillations and longitudinal emittance dilution of the storage ring electron beam resulting from photon-electron collisions without going to higher electron energy where the X-Ray energy spread becomes excessive for DSA. 38 refs.

Blumberg, L.N.

1992-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "factors sources calculations" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
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381

Hybrid Technique in SCALE for Fission Source Convergence Applied to Used Nuclear Fuel Analysis  

SciTech Connect

The new hybrid SOURCE ConveRgence accelERator (SOURCERER) sequence in SCALE deterministically computes a fission distribution and uses it as the starting source in a Monte Carlo eigenvalue criticality calculation. In addition to taking the guesswork out of defining an appropriate, problem-dependent starting source, the more accurate starting source provided by the deterministic calculation decreases the probability of producing inaccurate tally estimates associated with undersampling problems caused by inadequate source convergence. Furthermore, SOURCERER can increase the efficiency of the overall simulation by decreasing the number of cycles that has to be skipped before the keff accumulation. SOURCERER was applied to a representative example for a used nuclear fuel cask utilized at the Maine Yankee storage site {Scaglione and Ilas}. Because of the time constraints of the Used Fuel Research, Development, and Demonstration project, it was found that using more than 30,000 neutrons per cycle will lead to inaccurate Monte Carlo calculation of keff due to the inevitable decrease in the number of skipped and active cycles used with this problem. For a fixed uncertainty objective and by using 30,000 neutron per cycle, the use of SOURCERER increased the efficiency of the keff calculation by 60%compared to a Monte Carlo calculation that used a starting source distributed uniformly in fissionable regions, even with the inclusion of the extra computational time required by the deterministic calculation. Additionally, the use of SOURCERER increased the reliability of keff calculation using any number of skipped cycles below 350.

Ibrahim, Ahmad M [ORNL; Peplow, Douglas E. [ORNL; Bekar, Kursat B [ORNL; Celik, Cihangir [ORNL; Scaglione, John M [ORNL; Ilas, Dan [ORNL; Wagner, John C [ORNL

2013-01-01T23:59:59.000Z

382

Procedure for calculating interior daylight illumination with a programmable hand calculator  

DOE Green Energy (OSTI)

A procedure is described for calculating interior daylight illumination using an inexpensive programmable hand calculator. The proposed procedure calculates illumination at any point within a room utilizing sky luminance distribution functions that are consistent with the CIE (Commission Internationale de l'Eclairage) Overcast and Clear Sky functions. This procedure separates the light reaching the point being considered into three components, these being (a) light directly from the sky, (b) light after being reflected from external, and (c) internal surfaces. Finally, two examples are presented in order to demonstrate the proposed procedure and indicate the speed with which the calculations may be performed.

Bryan, H.J.; Clear, R.D.

1980-10-01T23:59:59.000Z

383

HP-67 CALCULATOR PROGRAMS FOR THERMODYNAMIC DATA AND PHASE DIAGRAM CALCULATIONS  

E-Print Network (OSTI)

Selected Values of the Thermodynamic Properties of theI-, Estimation of Thermodynamic D.ata and Phase Diagrams. ,CALCULATOR PROGRAMS FOR THERMODYNAMIC DATA AND PHASE DIAGRAM

Brewer, Leo

2010-01-01T23:59:59.000Z

384

Multipole Electrostatics in Hydration Free Energy Calculations  

E-Print Network (OSTI)

Multipole Electrostatics in Hydration Free Energy Calculations YUE SHI,1 CHUANJIE WU,2 JAY W. PONDER,2 PENGYU REN1 1 Department of Biomedical Engineering, The University of Texas, Austin, Texas 78712: Hydration free energy (HFE) is generally used for evaluating molecular solubility, which is an important

Ponder, Jay

385

Problems in electromagnetic mass-difference calculations  

SciTech Connect

A brief discussion is given on the progress made thus far in calculating the electromagnetic mass differences of elementary particles. Some of the methods discussed include Feynman's method, Cottinghams method, the methods involving Bjorken scaling iunctions, and the formalism of Dashen and Frautschi. (LBS)

Majumdar, D.P.

1972-01-01T23:59:59.000Z

386

URANIUM MILL TAILINGS RADON FLUX CALCULATIONS  

E-Print Network (OSTI)

URANIUM MILL TAILINGS RADON FLUX CALCULATIONS PI?ON RIDGE PROJECT MONTROSE COUNTY, COLORADO (EFRC) proposes to license, construct, and operate a conventional acid leach uranium and vanadium mill storage pad, and access roads. The mill is designed to process ore containing uranium and vanadium

387

Improved Calculation of Thermal Fission Energy  

E-Print Network (OSTI)

Thermal fission energy is one of the basic parameters needed in the calculation of antineutrino flux for reactor neutrino experiments. It is useful to improve the precision of the thermal fission energy calculation for current and future reactor neutrino experiments, which are aimed at more precise determination of neutrino oscillation parameters. In this article, we give new values for thermal fission energies of some common thermal reactor fuel isotopes, with improvements on three aspects. One is more recent input data acquired from updated nuclear databases. the second one is a consideration of the production yields of fission fragments from both thermal and fast incident neutrons for each of the four main fuel isotopes. The last one is more carefully calculation of the average energy taken away by antineutrinos in thermal fission with the comparison of antineutrino spectrum from different models. The change in calculated antineutrino flux due to the new values of thermal fission energy is about 0.32%, and the uncertainties of the new values are about 50% smaller.

X. B. Ma; W. L. Zhong; L. Z. Wang; Y. X. Chen; J. Cao

2012-12-29T23:59:59.000Z

388

Cool Roof Calculator | Open Energy Information  

Open Energy Info (EERE)

Cool Roof Calculator Cool Roof Calculator Jump to: navigation, search Tool Summary Name: Cool Roof Calculator Agency/Company /Organization: Oak Ridge National Laboratory Sector: Energy Focus Area: Buildings, Energy Efficiency Resource Type: Online calculator, Software/modeling tools User Interface: Website Website: www.ornl.gov/sci/roofs+walls/facts/CoolCalcEnergy.htm Country: United States Cost: Free Northern America Coordinates: 37.09024°, -95.712891° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":37.09024,"lon":-95.712891,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

389

National Synchrotron Light Source  

NLE Websites -- All DOE Office Websites (Extended Search)

All Documents listed below are part of the Photon Sciences Directorate and All Documents listed below are part of the Photon Sciences Directorate and will be updated as needed. Photon Sciences ESH Standard Operating Procedures (SOPs) SOP No. Standard Operating Procedure for: LS-ES-0002 Procedure for Acid Etching of Silicon and Germanium Crystals LS-ESH-0004 NSLS Operations Group Chemical Spill and Gas Release Response LS-ESH-0010 VUV Injection Shutter LOTO LS-ESH-0012 LINAC LOTO LS-ESH-0013 Controlled Access to the VUV Ring LS-ESH-0014 Radiation Safety Interlocks at the National Synchrotron Light Source LS-ESH-0019 Beam Line Configuration Control Checklist Requirements LS-ESH-0020 Biosafety Requirements at the NSLS LS-ESH-0021 Biosafety Level 2 work at the NSLS/ A Technical Basis LS-ESH-0022 Beam Line Configuration Control Checklist Requirements

390

Welcome | Advanced Photon Source  

NLE Websites -- All DOE Office Websites (Extended Search)

Welcome Welcome Aerial view of APS Aerial view of the APS Welcome to the Advanced Photon Source (APS) at Argonne National Laboratory. Whether you are a current or potential scientific user of our unique facility or are simply interested in learning more about the APS, we are delighted that you are visiting our website. The APS is funded by the Office of Science, Office of Basic Energy Sciences in the U.S. Department of Energy. We operate a National User Facility that is open to everyone who has a need for extremely brilliant x-ray photon beams. The APS is one of the most technologically complex machines in the world. This premier national research facility provides the brightest x-ray beams in the Western Hemisphere to more than 5,000 (and growing) scientists from

391

Thulium-170 heat source  

DOE Patents (OSTI)

An isotopic heat source is formed using stacks of thin individual layers of a refractory isotopic fuel, preferably thulium oxide, alternating with layers of a low atomic weight diluent, preferably graphite. The graphite serves several functions: to act as a moderator during neutron irradiation, to minimize bremsstrahlung radiation, and to facilitate heat transfer. The fuel stacks are inserted into a heat block, which is encased in a sealed, insulated and shielded structural container. Heat pipes are inserted in the heat block and contain a working fluid. The heat pipe working fluid transfers heat from the heat block to a heat exchanger for power conversion. Single phase gas pressure controls the flow of the working fluid for maximum heat exchange and to provide passive cooling.

Walter, Carl E. (Pleasanton, CA); Van Konynenburg, Richard (Livermore, CA); VanSant, James H. (Tracy, CA)

1992-01-01T23:59:59.000Z

392

Multiple source heat pump  

DOE Patents (OSTI)

A heat pump apparatus for conditioning a fluid characterized by a fluid handler and path for circulating a fluid in heat exchange relationship with a refrigerant fluid, at least three refrigerant heat exchangers, one for effecting heat exchange with the fluid, a second for effecting heat exchange with a heat exchange fluid, and a third for effecting heat exchange with ambient air; a compressor for compressing the refrigerant; at least one throttling valve connected at the inlet side of a heat exchanger in which liquid refrigerant is vaporized; a refrigerant circuit; refrigerant; a source of heat exchange fluid; heat exchange fluid circuit and pump for circulating the heat exchange fluid in heat exchange relationship with the refrigerant; and valves or switches for selecting the heat exchangers and directional flow of refrigerant therethrough for selecting a particular mode of operation. Also disclosed are a variety of embodiments, modes of operation, and schematics therefor.

Ecker, Amir L. (Duncanville, TX)

1983-01-01T23:59:59.000Z

393

Thulium-170 heat source  

SciTech Connect

An isotopic heat source is formed using stacks of thin individual layers of a refractory isotopic fuel, preferably thulium oxide, alternating with layers of a low atomic weight diluent, preferably graphite. The graphite serves several functions: to act as a moderator during neutron irradiation, to minimize bremsstrahlung radiation, and to facilitate heat transfer. The fuel stacks are inserted into a heat block, which is encased in a sealed, insulated and shielded structural container. Heat pipes are inserted in the heat block and contain a working fluid. The heat pipe working fluid transfers heat from the heat block to a heat exchanger for power conversion. Single phase gas pressure controls the flow of the working fluid for maximum heat exchange and to provide passive cooling.

Walter, C.E.; Van Konynenburg, R.; VanSant, J.H.

1990-09-06T23:59:59.000Z

394

ILC Positron source simualtion  

NLE Websites -- All DOE Office Websites (Extended Search)

(DOE Review 2007) (DOE Review 2007) Wanming Liu, Haitao Wang, Sergey Antipov, Wei Gai, Kwang-Je Kim HEP, ANL 04/27/2007 Where we are making contribution * Undulator radiation modeling * Adiabatic Matching Device modeling * Keep alive source simulation * Thermal dynamic study on windows * Eddy current simulation * Laser compton scheme positron production simulation for KEK/CLIC Where we are making contributions Outline Undulator and e+ yield OMD/AMD modeling and designing Thermal dynamic of target chamber window Energy deposition profile of target Collaboration with KEK/CLIC Comparison of positron yield from different undulators High K Devices Low K Devices BCD UK I UK II UK III Cornell I Cornell II Cornell III Period (mm) 10.0 11.5 11.0 10.5 10.0 12.0 7 0.3 0.46 28 ~0.54 Yield(Low Pol, 500m drift) ~2.13

395

Interferometry using undulator sources  

Science Conference Proceedings (OSTI)

Optical systems for extreme ultraviolet (EUV) lithography need to use optical components with subnanometer surface figure error tolerances to achieve diffraction-limited performance [M.D. Himel, in {ital Soft} {ital X}-{ital Ray} {ital Projection} {ital Lithography}, A.M. Hawryluk and R.H. Stulen, eds. (OSA, Washington, D.C., 1993), {bold 18}, 1089, and D. Attwood {ital et} {ital al}., Appl. Opt. {bold 32}, 7022 (1993)]. Also, multilayer-coated optics require at-wavelength wavefront measurement to characterize phase effects that cannot be measured by conventional optical interferometry. Furthermore, EUV optical systems will additionally require final testing and alignment at the operational wavelength for adjustment and reduction of the cumulative optical surface errors. Therefore, at-wavelength interferometric measurement of EUV optics will be the necessary metrology tool for the successful development of optics for EUV lithography. An EUV point diffraction interferometer (PDI) has been developed at the Center for X-Ray Optics (CXRO) and has been already in operation for a year [K. Goldberg {ital et} {ital al}., in {ital Extreme} {ital Ultra} {ital Lithography}, D.T. Attwood and F. Zernike, eds. (OSA, Washington, D.C., 1994), K. Goldberg {ital et} {ital al}., Proc. SPIE {bold 2437}, to be published, and K. Goldberg {ital et} {ital al}., J. Vac. Sci. Technol. B {bold 13}, 2923 (1995)] using an undulator radiation source and coherent optics beamline at the Advanced Light Source (ALS) at Lawrence Berkeley National Laboratory. An overview of the PDI interferometer and some EUV wavefront measurements obtained with this instrument will be presented. In addition, future developments planned for EUV interferometry at CXRO towards the measurement of actual EUV lithography optics will be shown. {copyright} {ital 1996 American Institute of Physics.}

Beguiristain, R.; Goldberg, K.A.; Tejnil, E.; Bokor, J.; Medecki, H.; Attwood, D.T.; Jackson, K. [Center for X-ray Optics, Lawrence Berkeley Laboratory, 1 Cyclotron Rd., MS 2-400, Berkeley, CA 94720 (United States)

1996-09-01T23:59:59.000Z

396

Testing the Role of Source Credibility on Memory for Inferences  

E-Print Network (OSTI)

Research shows that people have difficulty forgetting inferences they make after reading a passage, even when the information that the inferences are based on is later known to be untrue. This dissertation examined the effects of these inferences on memory for political information and tested if the credibility of the source of the correction influences whether people use the correction, or continue relying on the original information when making inferences. According to source credibility theory, there are two main factors that contribute to credibility, expertise and trustworthiness. Experiment 1 examined credibility as a function of both expertise and trustworthiness. The results from this experiment showed that having a correction from a source who is high on both factors significantly decreased the use of the original information. Experiment 2 examined credibility as a function of expertise. The Experiment 2 results showed no significant decrease in participants' use of the original information, if a correction came from a source that was simply more expert (but not more trustworthy) than another source. This finding suggests that source expertise alone is not sufficient to reduce reliance on the original information. Experiment 3, which examined credibility as a function of trustworthiness, demonstrated that having a highly trustworthy source does significantly decrease the use of the original information when making inferences. This study is the first to provide direct support for the hypothesis that making the source of a correction more believable decreases use of the original discredited information when making inferences.

Guillory, Jimmeka Joy

2011-08-01T23:59:59.000Z

397

Analysis of 3-panel and 4-panel microscale ionization sources  

Science Conference Proceedings (OSTI)

Two designs of a microscale electron ionization (EI) source are analyzed herein: a 3-panel design and a 4-panel design. Devices were fabricated using microelectromechanical systems technology. Field emission from carbon nanotube provided the electrons for the EI source. Ion currents were measured for helium, nitrogen, and xenon at pressures ranging from 10{sup -4} to 0.1 Torr. A comparison of the performance of both designs is presented. The 4-panel microion source showed a 10x improvement in performance compared to the 3-panel device. An analysis of the various factors affecting the performance of the microion sources is also presented. SIMION, an electron and ion optics software, was coupled with experimental measurements to analyze the ion current results. The electron current contributing to ionization and the ion collection efficiency are believed to be the primary factors responsible for the higher efficiency of the 4-panel microion source. Other improvements in device design that could lead to higher ion source efficiency in the future are also discussed. These microscale ion sources are expected to find application as stand alone ion sources as well as in miniature mass spectrometers.

Natarajan, Srividya; Parker, Charles B.; Glass, Jeffrey T. [Department of Electrical and Computer Engineering, Duke University, Durham, North Carolina 27708 (United States); Piascik, Jeffrey R.; Gilchrist, Kristin H. [Center for Materials and Electronic Technologies, RTI International, Research Triangle Park, North Carolina 27709 (United States); Stoner, Brian R. [Department of Electrical and Computer Engineering, Duke University, Durham, North Carolina 27708 (United States); Center for Materials and Electronic Technologies, RTI International, Research Triangle Park, North Carolina 27709 (United States)

2010-06-15T23:59:59.000Z

398

A global fouling factor methodology for analyzing steam generator thermal performance degradation  

Science Conference Proceedings (OSTI)

Over the past few years, steam generator (SG) thermal performance degradation has led to decreased plant efficiency and power output at numerous PWR nuclear power plants with recirculating-type SGs. The authors have developed and implemented methodologies for quantitatively evaluating the various sources of SG performance degradation, both internal and external to the SG pressure boundary. These methodologies include computation of the global fouling factor history, evaluation of secondary deposit thermal resistance using deposit characterization data, and consideration of pressure loss causes unrelated to the tube bundle, such as hot-leg temperature streaming and SG moisture separator fouling. In order to evaluate the utility of the global fouling factor methodology, the authors performed case studies for a number of PWR SG designs. Key results from two of these studies are presented here. In tandem with the fouling-factor analyses, a study evaluated for each plant the potential causes of pressure loss. The combined results of the global fouling factor calculations and the pressure-loss evaluations demonstrated two key points: (1) that the available thermal margin against fouling, which can vary substantially from plant to plant, has an important bearing on whether a given plant exhibits losses in electrical generating capacity, and (2) that a wide variety of causes can result in SG thermal performance degradation.

Kreider, M.A.; White, G.A.; Varrin, R.D. Jr. [Dominion Engineering, Inc., McLean, VA (United States)

1998-06-01T23:59:59.000Z

399

Relative Condition Factors of Fish as Bioindicators One Year after the Deepwater Horizon Oil Spill  

E-Print Network (OSTI)

Creel surveys were performed over a three week period in late spring, 2011, in the Lafourche and Calcasieu area estuaries of the Louisiana Gulf Coast. Weights and lengths were measured for black drum (Pogonias cromis), red drum (Sciaenops ocellatus), and spotted seatrout (Cynoscion nebulosus), and relative condition factors were calculated relative to expected weights from the long term (5 year) Louisiana data for each species. A normal relative condition factor is 1.00. The mean relative condition factors in the Lafourche area were black drum, 0.955 (0.020); red drum, 0.955 (0.011); spotted seatrout, 0.994 (0.009). In the Calcasieu area, the mean relative condition factors were black drum, 0.934 (0.017); red drum, 0.965 (0.014); spotted seatrout, 0.971 (0.010). Uncertainties are in parentheses. Results suggest that the abundance of primary food sources for black drum and red drum in Lafourche, including oysters and crab, were likely affected by the oil spill and continued to be reduced one year later. Increa...

Courtney, Joshua; Courtney, Amy; Torano, Joseph; Courtney, Michael

2012-01-01T23:59:59.000Z

400

Radiological Source Registry and Tracking  

NLE Websites -- All DOE Office Websites (Extended Search)

Radiological Source Registry and Tracking (RSRT) Radiological Source Registry and Tracking (RSRT) Home HSS Logo Radiological Source Registry and Tracking (RSRT) Department of Energy (DOE) Notice N 234.1 Reporting of Radioactive Sealed Sources has been superseded by DOE Order O 231.1B Environment, Safety and Health Reporting. O 231.1B identifies the requirements for centralized inventory and transaction reporting for radioactive sealed sources. Each DOE site/facility operator that owns, possesses, uses or maintains in custody those accountable radioactive sealed sources identified in Title 10 Code of Federal Regulation Part 835, Occupational Radiation Protection (10 CFR 835), Appendix E, and International Atomic Energy Agency (IAEA) Categories 1 and 2 radioactive sealed sources identified in Attachment 5, Appendix A of O 321.1B, will submit information to the DOE Radiological Source Registry and Tracking (RSRT) System.

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


401

Manhattan Project: Sources and Notes  

Office of Scientific and Technical Information (OSTI)

SOURCES AND NOTES SOURCES AND NOTES Resources > Sources Below are the collected specific notes for the text and images used on the pages of this web site. For a discussion of the most important works on the Manhattan Project, see the "Suggested Readings." For a general discussion of the use of sources in this web site, see "A Note on Sources." To scan the sources and notes for various categories, choose from the list below. To view the sources and notes for a specific web page, see the footnote at the bottom of each page (exceptions include this page and the home page; the sources and notes for the home page are the first ones listed below). Home Events 1890s-1939: Atomic Discoveries 1939-1942: Early Government Support 1942: Difficult Choices

402

Calculation of Kinetics Parameters for the NBSR  

Science Conference Proceedings (OSTI)

The delayed neutron fraction and prompt neutron lifetime have been calculated at different times in the fuel cycle for the NBSR when fueled with both high-enriched uranium (HEU) and low-enriched uranium (LEU) fuel. The best-estimate values for both the delayed neutron fraction and the prompt neutron lifetime are the result of calculations using MCNP5-1.60 with the most recent ENDFB-VII evaluations. The best-estimate values for the total delayed neutron fraction from fission products are 0.00665 and 0.00661 for the HEU fueled core at startup and end-of-cycle, respectively. For the LEU fuel the best estimate values are 0.00650 and 0.00648 at startup and end-of-cycle, respectively. The present recommendations for the delayed neutron fractions from fission products are smaller than the value reported previously of 0.00726 for the HEU fuel. The best-estimate values for the contribution from photoneutrons will remain as 0.000316, independent of the fuel or time in the cycle.The values of the prompt neutron lifetime as calculated with MCNP5-1.60 are compared to values calculated with two other independent methods and the results are in reasonable agreement with each other. The recommended, conservative values of the neutron lifetime for the HEU fuel are 650 {micro}s and 750 {micro}s for the startup and end-of-cycle conditions, respectively. For LEU fuel the recommended, conservative values are 600 {micro}s and 700 {micro}s for the startup and end-of-cycle conditions, respectively. In all three calculations, the prompt neutron lifetime was determined to be longer for the end-of-cycle equilibrium condition when compared to the startup condition. The results of the three analyses were in agreement that the LEU fuel will exhibit a shorter prompt neutron lifetime when compared to the HEU fuel.

Hanson A. L.; Diamond D.

2012-03-06T23:59:59.000Z

403

AQUIS: A PC-based source information manager  

SciTech Connect

The Air Quality Utility Information System (AQUIS) was developed to calculate emissions and track them along with related information about sources, stacks, controls, and permits. The system runs on IBM- compatible personal computers with dBASE IV and tracks more than 1, 200 data items distributed among various source categories. AQUIS is currently operating at 11 US Air Force facilities, which have up to 1, 000 sources, and two headquarters. The system provides a flexible reporting capability that permits users who are unfamiliar with database structure to design and prepare reports containing user- specified information. In addition to the criteria pollutants, AQUIS calculates compound-specific emissions and allows users to enter their own emission estimates.

Smith, A.E.; Huber, C.C.; Tschanz, J. [Argonne National Lab., IL (United States). Environmental Assessment and Information Sciences Div.; Ryckman, S.J. Jr. [Headquarters, Air Force Materiel Command, Wright-Patterson AFB, OH (United States). Environmental Engineering Div.

1993-05-01T23:59:59.000Z

404

AQUIS: A PC-based source information manager  

SciTech Connect

The Air Quality Utility Information System (AQUIS) was developed to calculate emissions and track them along with related information about sources, stacks, controls, and permits. The system runs on IBM- compatible personal computers with dBASE IV and tracks more than 1, 200 data items distributed among various source categories. AQUIS is currently operating at 11 US Air Force facilities, which have up to 1, 000 sources, and two headquarters. The system provides a flexible reporting capability that permits users who are unfamiliar with database structure to design and prepare reports containing user- specified information. In addition to the criteria pollutants, AQUIS calculates compound-specific emissions and allows users to enter their own emission estimates.

Smith, A.E.; Huber, C.C.; Tschanz, J. (Argonne National Lab., IL (United States). Environmental Assessment and Information Sciences Div.); Ryckman, S.J. Jr. (Headquarters, Air Force Materiel Command, Wright-Patterson AFB, OH (United States). Environmental Engineering Div.)

1993-01-01T23:59:59.000Z

405

Sources - CECM - Simon Fraser University  

E-Print Network (OSTI)

help annotate Contents Next: References Up: RamanujanModular Equations, Previous: Ramanujan's sum. Sources. [Annotate] [Shownotes]. References [7]...

406

Tracking of Moving Radioactive Sources  

Devices that detect the sources of unsecured nuclear materials are currently limited in their capabilities, ... City halls, public streets, hospitals ...

407

Neutron measurements and radiation damage calculations for fusion materials studies  

SciTech Connect

Fusion reactors will generate intense neutron fields, especially at the inner surfaces of containment vessels. With a typical wall loading of 1 MW/m/sup 2/, the yearly neutron fluence will be about 10/sup 26/ n/m/sup 2/. In a material like stainless steel this irradiation will produce about 10 atomic displacements-per-atom (DPA), 100 appM helium, 500 appM hydrogen, and various other transmutations. The gas-to-DPA ratios are very high compared to fission reactors due to the 14 MeV neutrons from the d-t fusion reaction. No existing neutron source can produce both the high fluence and high gas rates needed to simulate fusion damage. Consequently, fusion material studies are underway in a variety of facilities including fission reactors and accelerator-based neutron sources. A Subtask Group has been created by DOE to characterize these diverse facilities in terms of neutron flux and energy spectrum and to calculate DPA and transmutation for specific irradiations. Material property changes can then be correlated between facilities and extrapolated to fusion reactor conditions.

Greenwood, L.R.

1983-01-01T23:59:59.000Z

408

Heat Transfer Simulation of Reactor Cavity Cooling System Experimental Facility using RELAP5-3D and Generation of View Factors using MCNP  

E-Print Network (OSTI)

As one of the most attractive reactor types, The High Temperature Gas-cooled Reactor (HTGR) is designed to be passively safe with the incorporation of Reactor Cavity Cooling System (RCCS). In this paper, a RELAP5-3D simulation model is set up based on the 1/16 scale experimental facility established by Texas A&M University. Also, RELAP5-3D input decks are modified to replicate the experiment procedures and the experimental results are compared with the simulation results. The results show there is a perfect match between experimental and simulation results. Radiation heat transfer dominates in the heat transfer process of high temperature gas-cooled reactor due to its high operation temperature. According to experimental research done with the RCCS facility in Texas A&M University, radiation heat transfer takes up 80% of the total heat transferred to standing pipes. In radiation heat transfer, the important parameters are view factors between surfaces. However, because of the geometrical complexity in the experimental facility, it is hard to use the numerical method or analytical view factor formula to calculate view factors. In this project, MCNP based on the Monte Carlo method is used to generate view factors for RELAP5-3D input. MCNP is powerful in setting up complicated geometry, source definition and tally application. In the end, RCCS geometry is set up using MCNP and view factors are calculated.

Wu, Huali

2013-08-01T23:59:59.000Z

409

The Response of Balanced Hurricanes to Local Sources of Heat and Momentum  

Science Conference Proceedings (OSTI)

Eliassen's (1951) diagnostic technique is used to calculate the secondary circulation induced by point sources of heat and momentum in balanced, hurricane-like vortices. Scale analysis reveals that such responses are independent of the horizontal ...

Lloyd J. Shapiro; Huch E. Willoughby

1982-02-01T23:59:59.000Z

410

LS-35 6 GeV Light Source Storage Ring Quadrupole and Sextupole...  

NLE Websites -- All DOE Office Websites (Extended Search)

5 6 GeV Light Source Storage Ring Quadrupole and Sextupole Magnet Field Calculations Robert J. Lari September 23, 1985 Quadrupole Magnet Figure 1 shows the cross section of...

411

Rapid unbiased bipolar incoherent calculator cube  

Science Conference Proceedings (OSTI)

An electrooptical engagement array architecture for performing matrix-matrix multiplication using incoherent light is presented. Key components of this newly proposed processing device include a single pulsed incoherent light source, two dynamic light valves, and a two-dimensional photodetector array. 20 references.

Bocker, R.P.; Caulfield, H.F.; Bromley, K.

1983-01-01T23:59:59.000Z

412

" Row: NAICS Codes; Column: Energy Sources;"  

U.S. Energy Information Administration (EIA) Indexed Site

4 Number of Establishments by Offsite-Produced Fuel Consumption, 2002;" 4 Number of Establishments by Offsite-Produced Fuel Consumption, 2002;" " Level: National Data; " " Row: NAICS Codes; Column: Energy Sources;" " Unit: Establishment Counts." " "," "," ",," "," "," "," "," "," "," "," ",," " " "," ","Any",,,,,,,,,"RSE" "NAICS"," ","Energy",,"Residual","Distillate","Natural","LPG and",,"Coke"," ","Row" "Code(a)","Subsector and Industry","Source(b)","Electricity(c)","Fuel Oil","Fuel Oil(d)","Gas(e)","NGL(f)","Coal","and Breeze","Other(g)","Factors"

413

" Row: NAICS Codes; Column: Energy Sources;"  

U.S. Energy Information Administration (EIA) Indexed Site

4 Number of Establishments by Fuel Consumption, 2002;" 4 Number of Establishments by Fuel Consumption, 2002;" " Level: National Data; " " Row: NAICS Codes; Column: Energy Sources;" " Unit: Establishment Counts." " "," "," ",," "," "," "," "," "," "," "," ",," " " "," ","Any",,,,,,,,,"RSE" "NAICS"," ","Energy","Net","Residual","Distillate","Natural","LPG and",,"Coke"," ","Row" "Code(a)","Subsector and Industry","Source(b)","Electricity(c)","Fuel Oil","Fuel Oil(d)","Gas(e)","NGL(f)","Coal","and Breeze","Other(g)","Factors"

414

Radionuclide release calculations for selected severe accident scenarios  

Science Conference Proceedings (OSTI)

This report provides the results of source term calculations that were performed in support of the NUREG-1150 study. Severe Accident Risks: An Assessment for Five US Nuclear Power Plants.'' This is the sixth volume of a series of reports. It supplements results presented in the earlier volumes. Analyses were performed for three of the NUREG-1150 plants: Peach Bottom, a Mark I, boiling water reactor; Surry, a subatmospheric containment, pressurized water reactor; and Sequoyah, an ice condenser containment, pressurized water reactor. Complete source term results are presented for the following sequences: short term station blackout with failure of the ADS system in the Peach Bottom plant; station blackout with a pump seal LOCA for the Surry plant; station blackout with a pump seal LOCA in the Sequoyah plant; and a very small break with loss of ECC and spray recirculation in the Sequoyah plant. In addition, some partial analyses were performed which did not require running all of the modules of the Source Term Code Package. A series of MARCH3 analyses were performed for the Surry and Sequoyah plants to evaluate the effects of alternative emergency operating procedures involving primary and secondary depressurization on the progress of the accident. Only thermal-hydraulic results are provided for these analyses. In addition, three accident sequences were analyzed for the Surry plant for accident-induced failure of steam generator tubes. In these analyses, only the transport of radionuclides within the primary system and failed steam generator were examined. The release of radionuclides to the environment is presented for the phase of the accident preceding vessel meltthrough. 17 refs., 176 figs., 113 tabs.

Denning, R.S.; Leonard, M.T.; Cybulskis, P.; Lee, K.W.; Kelly, R.F.; Jordan, H.; Schumacher, P.M.; Curtis, L.A. (Battelle Columbus Div., OH (USA))

1990-08-01T23:59:59.000Z

415

Magnetic Flux of EUV Arcade and Dimming Regions as a Relevant Parameter for Early Diagnostics of Solar Eruptions - Sources of Non-Recurrent Geomagnetic Storms and Forbush Decreases  

E-Print Network (OSTI)

This study aims at the early diagnostics of geoeffectiveness of coronal mass ejections (CMEs) from quantitative parameters of the accompanying EUV dimming and arcade events. We study events of the 23th solar cycle, in which major non-recurrent geomagnetic storms (GMS) with Dst solar sources in the central part of the disk. Using the SOHO/EIT 195 A images and MDI magnetograms, we select significant dimming and arcade areas and calculate summarized unsigned magnetic fluxes in these regions at the photospheric level. The high relevance of this eruption parameter is displayed by its pronounced correlation with the Forbush decrease (FD) magnitude, which, unlike GMSs, does not depend on the sign of the Bz component but is determined by global characteristics of ICMEs. Correlations with the same magnetic flux in the solar source region are found for the GMS intensity (at the first step, without taking into account factors determining the Bz component near t...

Chertok, I M; Belov, A V; Abunin, A A

2012-01-01T23:59:59.000Z

416

factor.mws - CECM  

E-Print Network (OSTI)

... 0 "" {TEXT -1 61 "Be default \\+ factor factors over the field of rational numbers. ... {PARA 0 "> " 0 "" {MPLTEXT 1 0 36 "alias(beta=RootOf(x^5+x^3+x^2+x+1));" }...

417

Calculations of slurry pump jet impingement loads  

SciTech Connect

This paper presents a methodology to calculate the impingement load in the region of a submerged turbulent jet where a potential core exits and the jet is not fully developed. The profile of the jet flow velocities is represented by a piece-wise linear function which satisfies the conservation of momentum flux of the jet flow. The adequacy of the of the predicted jet expansion is further verified by considering the continuity of the jet flow from the region of potential core to the fully developed region. The jet impingement load can be calculated either as a direct impingement force or a drag force using the jet velocity field determined by the methodology presented.

Wu, T.T.

1996-03-04T23:59:59.000Z

418

Validation of Dose Calculation Codes for Clearance  

SciTech Connect

Various international and national bodies such as the International Atomic Energy Agency, the European Commission, the US Nuclear Regulatory Commission have put forward proposals or guidance documents to regulate the ''clearance'' from regulatory control of very low level radioactive material, in order to allow its recycling as a material management practice. All these proposals are based on predicted scenarios for subsequent utilization of the released materials. The calculation models used in these scenarios tend to utilize conservative data regarding exposure times and dose uptake as well as other assumptions as a safeguard against uncertainties. None of these models has ever been validated by comparison with the actual real life practice of recycling. An international project was organized in order to validate some of the assumptions made in these calculation models, and, thereby, better assess the radiological consequences of recycling on a practical large scale.

Menon, S.; Wirendal, B.; Bjerler, J.; Studsvik; Teunckens, L.

2003-02-27T23:59:59.000Z

419

CFD calculations of S809 aerodynamic characteristics  

DOE Green Energy (OSTI)

Steady-state, two-dimensional CFD calculations were made for the S809 laminar-flow, wind-turbine airfoil using the commercial code CFD-ACE. Comparisons of the computed pressure and aerodynamic coefficients were made with wind tunnel data from the Delft University 1.8 m x 1.25 m low-turbulence wind tunnel. This work highlights two areas in CFD that require further investigation and development in order to enable accurate numerical simulations of flow about current generation wind-turbine airfoils: transition prediction and turbulence modeling. The results show that the laminar-to-turbulent transition point must be modeled correctly to get accurate simulations for attached flow. Calculations also show that the standard turbulence model used in most commercial CFD codes, the k-{epsilon} model, is not appropriate at angles of attack with flow separation.

Wolfe, W.P. [Sandia National Labs., Albuquerque, NM (United States); Ochs, S.S. [Iowa State Univ., Ames, IA (United States)

1997-01-01T23:59:59.000Z

420

Asymptotic normalization coefficients from ab initio calculations.  

Science Conference Proceedings (OSTI)

We present calculations of asymptotic normalization coefficients (ANCs) for one-nucleon removals from nuclear states of mass numbers 3 {le} A {le} 9. Our ANCs were computed from variational Monte Carlo solutions to the many-body Schroedinger equation with the combined Argonne v{sub 18} two-nucleon and Urbana IX three-nucleon potentials. Instead of computing explicit overlap integrals, we applied a Green function method that is insensitive to the difficulties of constructing and Monte Carlo sampling the long-range tails of the variational wave functions. This method also allows computation of the ANC at the physical separation energy, even when it differs from the separation energy for the Hamiltonian. We compare our results, which for most nuclei are the first ab initio calculations of ANCs, with existing experimental and theoretical results and discuss further possible applications of the technique.

Nollett, K. M.; Wiringa, R. B. (Physics)

2011-04-13T23:59:59.000Z

Note: This page contains sample records for the topic "factors sources calculations" from the National Library of EnergyBeta (NLEBeta).
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to obtain the most current and comprehensive results.


421

Advanced Light Source  

NLE Websites -- All DOE Office Websites (Extended Search)

Next >> Next >> Visitors Access to the ALS Gate Access guest-house Guest House lab-shuttles Lab Shuttles maps-and-directions Maps and Directions Parking Safety Safety for Users safety-for-staff Safety for Staff In Case of Emergency Resources Acronyms Multimedia Employment staff-intranet Staff Intranet Site Map Contact Digg: ALSBerkeleyLab Facebook Page: 208064938929 Flickr: advancedlightsource Twitter: ALSBerkeleyLab YouTube: AdvancedLightSource January 2014 Sun Mon Tue Wed Thu Fri Sat 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 Recent Science Highlights Minding the Gap Makes for More Efficient Solar Cells Using novel materials to develop thin, flexible, and more efficient photovoltaic cells is one of the hottest topics in current materials research. A class of transition metals undergo a dramatic change that makes them ideal for solar energy applications.

422

Steam Generator Management Program: Flaw Handbook Calculator  

Science Conference Proceedings (OSTI)

The EPRI Steam Generator Management Program: Steam Generator Degradation Specific Flaw Handbook v1.0 defines burst pressure equations for steam generator tubes with various degradation morphologies, and the EPRI Steam Generator Management Program: Steam Generator Integrity Assessment Guidelines (1019038) describes a probabilistic evaluation process which can be used to account for key input parameter uncertainties. The Flaw Handbook Calculator software is an automated Microsoft Excelspreadsheet which cal...

2010-04-20T23:59:59.000Z

423

Bases for pump pit requirements calculations  

DOE Green Energy (OSTI)

A task team is preparing the Process Requirements for the interarea transfer pump pits at the Defense Waste Process Facility (DWPF). The team is developing requirements to prevent flammable mixtures from forming and requires values to use on the generation of various components such as benzene, hydrogen, and N20. The purpose of this memorandum is to document values to be used and to provide sample calculations using these values. There are no recommendations contained in this document.

Jacobs, R.A.

1992-02-13T23:59:59.000Z

424

Free Energy Calculation in MD Simulation  

E-Print Network (OSTI)

Free Energy Calculation in MD Simulation #12;Basic Thermodynamics Helmoholtz free energy A = U ­ TS + i Ni dA = wrev (reversible, const N V T) eq (22.9) McQuarrie & Simon Gibbs free energy G = U;Implication of Free Energy A B Keq = [A]/[B] Keq = exp (-G0 /RT) G0 = -RT ln Keq G = G0 + RT ln Q G > 0

Nielsen, Steven O.

425

Vestibule and Cask Preparation Mechanical Handling Calculation  

SciTech Connect

The scope of this document is to develop the size, operational envelopes, and major requirements of the equipment to be used in the vestibule, cask preparation area, and the crane maintenance area of the Fuel Handling Facility. This calculation is intended to support the License Application (LA) submittal of December 2004, in accordance with the directive given by DOE correspondence received on the 27th of January 2004 entitled: ''Authorization for Bechtel SAIC Company L.L.C. to Include a Bare Fuel Handling Facility and Increased Aging Capacity in the License Application, Contract Number DE-AC28-01R W12101'' (Ref. 167124). This correspondence was appended by further correspondence received on the 19th of February 2004 entitled: ''Technical Direction to Bechtel SAIC Company L.L. C. for Surface Facility Improvements, Contract Number DE-AC28-01R W12101; TDL No. 04-024'' (Ref. 16875 1). These documents give the authorization for a Fuel Handling Facility to be included in the baseline. The limitations of this preliminary calculation lie within the assumptions of section 5 , as this calculation is part of an evolutionary design process.

N. Ambre

2004-05-26T23:59:59.000Z

426

A comparison of world-wide uses of severe reactor accident source terms  

SciTech Connect

The definitions of source terms to reactor containments and source terms to the environment are discussed. A comparison is made between the TID-14844 example source term and the alternative source term described in NUREG-1465. Comparisons of these source terms to the containments and those used in France, Germany, Japan, Sweden, and the United Kingdom are made. Source terms to the environment calculated in NUREG-1500 and WASH-1400 are discussed. Again, these source terms are compared to those now being used in France, Germany, Japan, Sweden, and the United Kingdom. It is concluded that source terms to the containment suggested in NUREG-1465 are not greatly more conservative than those used in other countries. Technical bases for the source terms are similar. The regulatory use of the current understanding of radionuclide behavior varies among countries.

Ang, M.L. [NNC Ltd., Knutsford (United Kingdom); Frid, W. [Swedish Nuclear Power Inspectorate, Stockholm (Sweden); Kersting, E.J.; Friederichs, H.G. [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Koeln (Germany); Lee, R.Y. [Nuclear Regulatory Commission, Washington, DC (United States); Meyer-Heine, A. [CEA Centre d`Etudes de Cadarache, Saint Paul Lez Durance (France); Powers, D.A. [Sandia National Labs., Albuquerque, NM (United States); Soda, K. [Japan Atomic Energy Research Inst., Tokyo (Japan); Sweet, D. [AEA Technology, Winfrith (United Kingdom)

1994-09-01T23:59:59.000Z

427

Dose factor entry and display tool for BNCT radiotherapy  

DOE Patents (OSTI)

A system for use in Boron Neutron Capture Therapy (BNCT) radiotherapy planning where a biological distribution is calculated using a combination of conversion factors and a previously calculated physical distribution. Conversion factors are presented in a graphical spreadsheet so that a planner can easily view and modify the conversion factors. For radiotherapy in multi-component modalities, such as Fast-Neutron and BNCT, it is necessary to combine each conversion factor component to form an effective dose which is used in radiotherapy planning and evaluation. The Dose Factor Entry and Display System is designed to facilitate planner entry of appropriate conversion factors in a straightforward manner for each component. The effective isodose is then immediately computed and displayed over the appropriate background (e.g. digitized image).

Wessol, Daniel E. (Bozeman, MT); Wheeler, Floyd J. (Idaho Falls, ID); Cook, Jeremy L. (Greeley, CO)

1999-01-01T23:59:59.000Z

428

Key Factors in Displacement Ventilation Systems for Better IAQ  

E-Print Network (OSTI)

This paper sets up a mathematical model of three-dimensional steady turbulence heat transfer in an air-conditioned room of multi-polluting heat sources. Numerical simulation helps identify key factors in displacement ventilation systems that affect air-quality in rooms of multi-polluting heat sources. Results show that it is very important to determine the suitable air-intemperature , air-inflow, and heat source quantity and dispersion, to obtain better displacement ventilation results.

Wang, X.; Chen, J.; Li, Y.; Wang, Z.

2006-01-01T23:59:59.000Z

429

Detailed Burnup Calculations for Testing Nuclear Data  

Science Conference Proceedings (OSTI)

A general method (MCQ) has been developed by introducing a microscopic burnup scheme that uses the Monte Carlo calculated fluxes and microscopic reaction rates of a complex system and a depletion code for burnup calculations as a basis for solving nuclide material balance equations for each spatial region in which the system is divided. Continuous energy-dependent cross-section libraries and full 3D geometry of the system can be input for the calculations. The resulting predictions for the system at successive burnup time steps are thus based on a calculation route where both geometry and cross sections are accurately represented, without geometry simplifications and with continuous energy data, providing an independent approach for benchmarking other methods and nuclear data of actinides, fission products, and other burnable absorbers. The main advantage of this method over the classical deterministic methods currently used is that the MCQ System is a direct 3D method without the limitations and errors introduced on the homogenization of geometry and condensation of energy of deterministic methods. The Monte Carlo and burnup codes adopted until now are the widely used MCNP and ORIGEN codes, but other codes can be used also. For using this method, there is need of a well-known set of nuclear data for isotopes involved in burnup chains, including burnable poisons, fission products, and actinides. For fixing the data to be included in this set, a study of the present status of nuclear data is performed, as part of the development of the MCQ method. This study begins with a review of the available cross-section data of isotopes involved in burnup chains for power and research nuclear reactors. The main data needs for burnup calculations are neutron cross sections, decay constants, branching ratios, fission energy, and yields. The present work includes results of selected experimental benchmarks and conclusions about the sensitivity of different sets of cross-section data for burnup calculations, using some of the main available evaluated nuclear data files (ENDF-B-VI-Rel.8, JEFF-3.0, JENDL-3.3), on an isotope-by-isotope basis as much as possible. The selected experimental burnup benchmarks are reference cases for LWR and HWR reactors, with analysis of isotopic composition as a function of burnup. For LWR (H2O-moderated uranium oxide lattices) four benchmarks are included: ATM-104 NEA Burnup credit criticality benchmark; Yankee-Rowe Core V; H.B.Robinson Unit 2 and Turkey Point Unit 3. For HWR (D2O-moderated uranium oxide cluster lattices), three benchmarks were selected: NPD-19-rod Fuel Clusters; Pickering-28-rod Fuel Clusters; and Bruce-37-rod Fuel Clusters. The isotopes with experimental concentration data included in these benchmarks are: Se-79, Sr90, Tc99, Ru106, Sn126, Sb125,1129, Cs133-137, Nd143, 145, Sm149-150, 152, Eul53-155, U234-235, 238, Np237, Pu238-242, Am241-243, and Cm242-248. Results and analysis of differences between calculated and measured absolute and/or relative concentrations of these isotopes for the seven benchmarks are included in this work.

Leszczynski, F. [Centro Atomico Bariloche (CNEA), 8400 S.C.de Bariloche (Argentina)

2005-05-24T23:59:59.000Z

430

Source Attribution of Light Absorbing Aerosol in Arctic Snow  

NLE Websites -- All DOE Office Websites (Extended Search)

Source Attribution of Light Absorbing Source Attribution of Light Absorbing Aerosol in Arctic Snow (Preliminary analysis of 2008-2009 data) Outline * Receptor modeling overview * Results from 2007 data set * New goals arising from analysis of 2007 data * New data for 2008 * New data for 2009 * Tentative conclusions * Future analysis i Factor profiles from 2007 analysis Source attribution of Black Carbon from 2007 analysis Goals/Issues suggested by the analysis of the 2007 data set * Are there seasonal differences in the source strengths? * Are there other LAA chemical components besides black carbon. What are their sources? * Can the various data sets available (e.g., 2007, 2008, 2009) be combined in a single large PMF analysis 2008 Data Set For Receptor Analysis * 42 samples from Eastern Siberia including 4 depth profiles

431

Electronic equilibrium as a function of depth in tissue from Cobalt-60 point source exposures  

E-Print Network (OSTI)

The Nuclear Regulatory Commission has set the basic criteria for assessing skin dose stemming from hot particle contaminations. Compliance with IO CFR 20. 1 01 requires that exposure to the skin be evaluated over a I CM2 area at a depth of 0.007 cm. Skin exposure can arise from both the beta and gamma components of radioactive particles and gamma radiation can contribute significantly to skin doses. The gamma component of dose increases dramatically when layers of protective clothing are interposed between the hot particle source and the skin, and in cases where the hot particle is large in comparison to the range of beta particles. Once the protective clothing layer is thicker than the maximum range of the beta particles, skin dose is due solely to gamma radiation. Charged particle equilibrium is not established at shallow depths. The degree of electronic equilibrium establishment must be assessed for shallow doses to prevent the overassessment of skin dose because conventional fluence-to-dose conversion factors are not applicable. To assess the effect of electronic equilibrium, selected thicknesses of tissue equivalent material were interposed between radiochromic dye film and a 6OCo hot particle source and dose was measured as a function of depth. These measured values were then compared to models which are used to calculate charged particle equilibrium. The Miller-Reece model was found to agree closely with the experimental data while the Lantz-Lambert model overestimated dose at shallow depths.

Myrick, Jo Ann

1994-01-01T23:59:59.000Z

432

Burnup calculation by the method of first-flight collision probabilities using average chords prior to the first collision  

Science Conference Proceedings (OSTI)

A technique to calculate the burnup of materials of cells and fuel assemblies using the matrices of first-flight neutron collision probabilities rebuilt at a given burnup step is presented. A method to rebuild and correct first collision probability matrices using average chords prior to the first neutron collision, which are calculated with the help of geometric modules of constructed stochastic neutron trajectories, is described. Results of calculation of the infinite multiplication factor for elementary cells with a modified material composition compared to the reference one as well as calculation of material burnup in the cells and fuel assemblies of a VVER-1000 are presented.

Karpushkin, T. Yu., E-mail: timka83@yandex.ru [Russian Research Centre Kurchatov Institute (Russian Federation)

2012-12-15T23:59:59.000Z

433

ALLDOS: a computer program for calculation of radiation doses from airborne and waterborne releases  

Science Conference Proceedings (OSTI)

The computer code ALLDOS is described and instructions for its use are presented. ALLDOS generates tables of radiation doses to the maximum individual and the population in the region of the release site. Acute or chronic release of radionuclides may be considered to airborne and waterborne pathways. The code relies heavily on data files of dose conversion factors and environmental transport factors for generating the radiation doses. A source inventory data library may also be used to generate the release terms for each pathway. Codes available for preparation of the dose conversion factors are described and a complete sample problem is provided describing preparation of data files and execution of ALLDOS.

Strenge, D.L.; Napier, B.A.; Peloquin, R.A.; Zimmerman, M.G.

1980-10-01T23:59:59.000Z

434

rf improvements for Spallation Neutron Source H{sup -} ion source  

SciTech Connect

The Spallation Neutron Source at Oak Ridge National Laboratory is ramping up the accelerated proton beam power to 1.4 MW and just reached 1 MW. The rf-driven multicusp ion source that originates from the Lawrence Berkeley National Laboratory has been delivering {approx}38 mA H{sup -} beam in the linac at 60 Hz, 0.9 ms. To improve availability, a rf-driven external antenna multicusp ion source with a water-cooled ceramic aluminum nitride (AlN) plasma chamber is developed. Computer modeling and simulations have been made to analyze and optimize the rf performance of the new ion source. Operational statistics and test runs with up to 56 mA medium energy beam transport beam current identify the 2 MHz rf system as a limiting factor in the system availability and beam production. Plasma ignition system is under development by using a separate 13 MHz system. To improve the availability of the rf power system with easier maintenance, we tested a 70 kV isolation transformer for the 80 kW, 6% duty cycle 2 MHz amplifier to power the ion source from a grounded solid-state amplifier.

Kang, Y. W.; Fuja, R.; Hardek, T.; Lee, S.-W.; McCarthy, M. P.; Piller, M. C.; Shin, K.; Stockli, M. P.; Welton, R. F. [Spallation Neutron Source, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831 (United States); Goulding, R. H. [Fusion Energy Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831 (United States)

2010-02-15T23:59:59.000Z

435

Source Apportionment of Airborne Particulate Matter using Inorganic and  

NLE Websites -- All DOE Office Websites (Extended Search)

Source Apportionment of Airborne Particulate Matter using Inorganic and Source Apportionment of Airborne Particulate Matter using Inorganic and Organic Species as Tracers Title Source Apportionment of Airborne Particulate Matter using Inorganic and Organic Species as Tracers Publication Type Journal Article Year of Publication 2012 Authors Wang, Yungang, Philip K. Hopke, X. Xia, Oliver V. Rattigan, David C. Chalupa, and M. J. Source Journal Atmospheric Environment Volume 55 Start Page 525 Pagination 525-532 Date Published 01/2012 Keywords source apportionment positive matrix factorization (pmf) particulate matter (pm) molecular markers (mm) aethalometer delta-c Abstract Source apportionment is typically performed on chemical composition data derived from particulate matter (PM) samples. However, many common sources no longer emit significant amounts of characteristic trace elements requiring the use of more comprehensive chemical characterization in order to fully resolve the PM sources. Positive matrix factorization (EPA PMF, version 4.1) was used to analyze 24-hr integrated molecular marker (MM), secondary inorganic ions, trace elements, carbonaceous species and light absorption data to investigate sources of PM2.5 in Rochester, New York between October 2009 and October 2010 to explore the role of specific MMs. An eight-factor solutionwas found for which the factors were identified as isoprene secondary organic aerosol (SOA), airborne soil, other SOA, diesel emissions, secondary sulfate, wood combustion, gasoline vehicle, and secondary nitrate contributing 6.9%, 12.8%, 3.7%, 7.8%, 45.5%, 9.1%, 7.9%, and 6.3% to the average PM2.5 concentration, respectively Concentrations of pentacosane, hexacosane, heptacosane, and octacosane in the gasoline vehicles factor were larger compared to diesel emissions. Aethalometer Delta-C was strongly associated with wood combustion. The compounds, n-heptacosanoic acid and n-octacosanoic acid, occasionally used in the past as tracers for road dust, were found to largely associate with SOA in this study. In comparison with a standard PMF analyses without MM, inclusion of themwas necessary to resolve SOA and wood combustion factors in urban areas.

436

SOLAR MIXTURE OPACITY CALCULATIONS USING DETAILED CONFIGURATION AND LEVEL ACCOUNTING TREATMENTS  

Science Conference Proceedings (OSTI)

An opacity model (OPAS) combining detailed configuration and level accounting treatments has been developed to calculate radiative opacity of plasmas in local thermodynamic equilibrium. The model is presented and used to compute spectral opacities of a solar mixture. Various density-temperature couples have been considered from the solar center up to the vicinity of the radiative/convective zone interface. For a given solar thermodynamic path, OPAS calculations are compared to Opacity Project (OP) and OPAL data. Rosseland mean opacity values are in very good agreement over all the considered solar thermodynamic path, while OPAS and OP spectral opacities of each element may vary considerably. Main sources of discrepancy are discussed.

Blancard, Christophe; Cosse, Philippe; Faussurier, Gerald [CEA, DAM, DIF, F-91297 Arpajon (France)

2012-01-20T23:59:59.000Z

437

The Origins of the SPAR-H Method's Performance Shaping Factor Multipliers  

Science Conference Proceedings (OSTI)

The Standardized Plant Analysis Risk-Human Reliability Analysis (SPAR-H) method has proved to be a reliable, easy-to-use method for human reliability analysis. Calculation of human error probability (HEP) rates is especially straightforward, starting with pre-defined nominal error rates for cognitive vs. action oriented tasks, and incorporating performance shaping factor (PSF) multipliers upon those nominal error rates. SPAR-H uses eight PSFs with multipliers typically corresponding to nominal, degraded, and severely degraded human performance for individual PSFs. Additionally, some PSFs feature multipliers to reflect enhanced performance. Although SPAR-H enjoys widespread use among industry and regulators, current source documents on SPAR-H such as NUREG/CR-6883 do not provide a clear account of the origin of these multipliers. The present paper redresses this shortcoming and documents the historic development of the SPAR-H PSF multipliers, from the initial use of nominal error rates, to the selection of the eight PSFs, to the mapping of multipliers to available data sources such as a Technique for Human Error Rate Prediction (THERP). Where error rates were not readily derived from THERP and other sources, expert judgment was used to extrapolate appropriate values. In documenting key background information on the multipliers, this paper provides a much needed cross-reference for human reliability practitioners and researchers of SPAR-H to validate analyses and research findings.

Ronald L. Boring; Harold S. Blackman

2007-08-01T23:59:59.000Z

438

Energy Efficiency CO2 Intensity Calculator (EE-CO2 Intensity Calculator) Version 3.0  

Science Conference Proceedings (OSTI)

This spreadsheet calculator will allow members to quantify the impact of their energy efficiency savings and fuel displacement on carbon-dioxide emissions, specific to their region and the end-uses ...

2012-12-13T23:59:59.000Z

439

Seven health physics calculator programs for the HP-41CV  

Science Conference Proceedings (OSTI)

Several user-oriented programs for the Hewlett-Packard HP-41CV are explained. The first program builds, stores, alters, and ages a list of radionuclides. This program only handles single- and double-decay chains. The second program performs convenient conversions for the six nuclides of concern in plutonium handling. The conversions are between mass, activity, and weight percents of the isotopes. The source can be aged and/or neutron generation rates can be computed. The third program is a timekeeping program that improves the process of manually estimating and tracking personnel exposure during high dose rate tasks by replacing the pencil, paper, and stopwatch method. This program requires a time module. The remaining four programs deal with computations of time-integrated air concentrations at various distances from an airborne release. Building wake effects, source depletion by ground deposition, and sector averaging can all be included in the final printout of the X/Q - Hanford and X/Q - Pasquill programs. The shorter versions of these, H/Q and P/Q, compute centerline or sector-averaged values and include a subroutine to facilitate dose estimation by entering dose factors and quantities released. The horizontal and vertical dispersion parameters in the Pasquill-Gifford programs were modeled with simple, two-parameter functions that agreed very well with the usual textbook graphs. 8 references, 7 appendices.

Rittmann, P.D.

1984-08-01T23:59:59.000Z

440

H{sup -} radio frequency source development at the Spallation Neutron Source  

Science Conference Proceedings (OSTI)

The Spallation Neutron Source (SNS) now routinely operates nearly 1 MW of beam power on target with a highly persistent {approx}38 mA peak current in the linac and an availability of {approx}90%. H{sup -} beam pulses ({approx}1 ms, 60 Hz) are produced by a Cs-enhanced, multicusp ion source closely coupled with an electrostatic low energy beam transport (LEBT), which focuses the 65 kV beam into a radio frequency quadrupole accelerator. The source plasma is generated by RF excitation (2 MHz, {approx}60 kW) of a copper antenna that has been encased with a thickness of {approx}0.7 mm of porcelain enamel and immersed into the plasma chamber. The ion source and LEBT normally have a combined availability of {approx}99%. Recent increases in duty-factor and RF power have made antenna failures a leading cause of downtime. This report first identifies the physical mechanism of antenna failure from a statistical inspection of {approx}75 antennas which ran at the SNS, scanning electron microscopy studies of antenna surface, and cross sectional cuts and analysis of calorimetric heating measurements. Failure mitigation efforts are then described which include modifying the antenna geometry and our acceptance/installation criteria. Progress and status of the development of the SNS external antenna source, a long-term solution to the internal antenna problem, are then discussed. Currently, this source is capable of delivering comparable beam currents to the baseline source to the SNS and, an earlier version, has briefly demonstrated unanalyzed currents up to {approx}100 mA (1 ms, 60 Hz) on the test stand. In particular, this paper discusses plasma ignition (dc and RF plasma guns), antenna reliability, magnet overheating, and insufficient beam persistence.

Welton, R. F.; Gawne, K. R.; Han, B. X.; Murray, S. N.; Pennisi, T. R.; Roseberry, R. T.; Santana, M.; Stockli, M. P. [Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, Tennessee 37830-6471 (United States); Dudnikov, V. G. [Muons, Inc., 552 N. Batavia Avenue, Batavia, Illinois 60510 (United States); Turvey, M. W. [Villanova University, 800E. Lancaster Ave, Villanova, Pennsylvania 19085 (United States)

2012-02-15T23:59:59.000Z

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


441

Neutron Form Factor from Neutrino-Nucleus Coherent Elastic Scattering  

E-Print Network (OSTI)

We analyze the prospect of measuring the neutron form factor of a nucleus through the detection of neutrino-nucleus coherent elastic scattering. We predict numbers of events in a liquid noble nuclear recoil detector at a stopped pion neutrino source. We discuss the precision required to distinguish between different theoretical models for the form factor.

Philip S. Amanik; Gail C. McLaughlin

2007-07-27T23:59:59.000Z

442

Light Sources Directorate Strategic Plan  

NLE Websites -- All DOE Office Websites (Extended Search)

Light Sources Directorate Light Sources Directorate Strategic Plan December 2009 Light Sources Directorate Strategic Plan December 2009 ii | Vision and Mission Light Sources Directorate Strategic Plan The VISION of the Light Sources Directorate is: to be a provider of choice for world-class photon science and facilities that deliver outstanding scientific productivity and impact, and to be recognized as a leader in developing innovative techniques and ap- plications of photon science Our MISSION is defined by the set of activities that are required to realize this vision: to advance scientific knowledge and to solve critical problems through the design, construction, operation, and use of premier photon science facilities | Table of Contents Light Sources Directorate Strategic Plan

443

Constricted glow discharge plasma source  

SciTech Connect

A constricted glow discharge chamber and method are disclosed. The polarity and geometry of the constricted glow discharge plasma source is set so that the contamination and energy of the ions discharged from the source are minimized. The several sources can be mounted in parallel and in series to provide a sustained ultra low source of ions in a plasma with contamination below practical detection limits. The source is suitable for applying films of nitrides such as gallium nitride and oxides such as tungsten oxide and for enriching other substances in material surfaces such as oxygen and water vapor, which are difficult process as plasma in any known devices and methods. The source can also be used to assist the deposition of films such as metal films by providing low-energy ions such as argon ions.

Anders, Andre (Albany, CA); Anders, Simone (Albany, CA); Dickinson, Michael (San Leandro, CA); Rubin, Michael (Berkeley, CA); Newman, Nathan (Winnetka, IL)

2000-01-01T23:59:59.000Z

444

electricity emission factors | OpenEI  

Open Energy Info (EERE)

emission factors emission factors Dataset Summary Description Emissions from energy use in buildings are usually estimated on an annual basis using annual average multipliers. Using annual numbers provides a reasonable estimation of emissions, but it provides no indication of the temporal nature of the emissions. Therefore, there is no way of understanding the impact on emissions from load shifting and peak shaving technologies such as thermal energy storage, on-site renewable energy, and demand control. Source NREL Date Released April 11th, 2011 (3 years ago) Date Updated April 11th, 2011 (3 years ago) Keywords buildings carbon dioxide emissions carbon footprinting CO2 commercial buildings electricity emission factors ERCOT hourly emission factors interconnect nitrogen oxides

445

Energy Department Report Calculates Emissions and Costs of Power...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Report Calculates Emissions and Costs of Power Plant Cycling Necessary for Increased Wind and Solar in the West Energy Department Report Calculates Emissions and Costs of Power...

446

Illustrative Calculation of Economics for Heat Pump and "Grid...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Illustrative Calculation of Economics for Heat Pump and "Grid-Enabled" Water Heaters Illustrative Calculation of Economics for Heat Pump and "Grid-Enabled" Water Heaters Rate...

447

Using EnergyPlus for California Title-24 compliance calculations  

NLE Websites -- All DOE Office Websites (Extended Search)

Using EnergyPlus for California Title-24 compliance calculations Title Using EnergyPlus for California Title-24 compliance calculations Publication Type Conference Paper LBNL...

448

Documentation of Calculation Methodology, Input Data, and Infrastructu...  

NLE Websites -- All DOE Office Websites (Extended Search)

Documentation of Calculation Methodology, Input Data, and Infrastructure for the Home Energy Saver Web Site Title Documentation of Calculation Methodology, Input Data, and...

449

Introduction to the Cash Flow Opportunity Calculator Spreadsheet...  

NLE Websites -- All DOE Office Websites (Extended Search)

Calculator is an interactive calculator that helps quantify the cost of delaying investment in upgrades by addressing three critical questions: How much new energy efficiency...

450

FEMP Solar Hot Water Calculator | Open Energy Information  

Open Energy Info (EERE)

Solar Hot Water Calculator Jump to: navigation, search Name FEMP Solar Hot Water Calculator Abstract Online tool to help Federal agencies meet Energy Independence and Security Act...

451

Optically pumped polarized ion sources  

SciTech Connect

Polarization transfer collisions between protons, atomic hydrogen, or deuterium and optically pumped alkali-metal vapour are implemented in the high current optically pumped polarized ion source (OPPIS) and the laser driven source (LDS) of nuclear polarized atoms for target applications. The OPPIS technique overcomes the limitations on intensity of the conventional atomic beam source technique and meets the requirements of the new generation of polarization experiments at multi-GeV accelerators and colliders. 17 refs., 3 figs.

Zelenski, A.N.

1995-12-31T23:59:59.000Z

452

Discussions on Disposal Forms of Auxiliary Heat Source in Surface Water Heat Pump System  

E-Print Network (OSTI)

This paper presents two common forms of auxiliary heat source in surface water heat pump system and puts forward the idea that the disposal forms affect operation cost. It deduces operation cost per hour of the two forms. With a project calculation, it illuminates that the post-located auxiliary heat source cheaper and superior to the fore-located one.

Qian, J.; Sun, D.; Li, X.; Li, G.

2006-01-01T23:59:59.000Z

453

Search for Spatially Extended Fermi-LAT Sources Using Two Years of Data  

SciTech Connect

Spatial extension is an important characteristic for correctly associating {gamma}-ray-emitting sources with their counterparts at other wavelengths and for obtaining an unbiased model of their spectra. We present a new method for quantifying the spatial extension of sources detected by the Large Area Telescope (LAT), the primary science instrument on the Fermi Gamma-ray Space Telescope (Fermi). We perform a series of Monte Carlo simulations to validate this tool and calculate the LAT threshold for detecting the spatial extension of sources. We then test all sources in the second Fermi -LAT catalog (2FGL) for extension. We report the detection of seven new spatially extended sources.

Lande, Joshua; Ackermann, Markus; Allafort, Alice; Ballet, Jean; Bechtol, Keith; Burnett, Toby; Cohen-Tanugi, Johann; Drlica-Wagner, Alex; Funk, Stefan; Giordano, Francesco; Grondin, Marie-Helene; Kerr, Matthew; Lemoine-Goumard, Marianne

2012-07-13T23:59:59.000Z

454

ARC SNUBBERS NEUTRAL BEAM SOURCES  

E-Print Network (OSTI)

transformer cores near the source and route all of the powertransformer that transiently separates the energy in the capacitances of the power

Baker, W.R.

2011-01-01T23:59:59.000Z

455

Tsunami Information Sources: Part 3  

E-Print Network (OSTI)

A Landslide in the Upper Aleutian Forearc,' by G.J. Fryer,of the Source of the 1946 Aleutian 'Tsunami' Earthquake,"

Wiegel, Robert L.

2006-01-01T23:59:59.000Z

456

Relative risks of energy sources  

Science Conference Proceedings (OSTI)

This paper compares the risks associated with various energy sources in an attempt to demonstrate the relative safety of nuclear energy. (JEF)

Haire, M.J.

1990-01-01T23:59:59.000Z

457

Video Library | Advanced Photon Source  

NLE Websites -- All DOE Office Websites (Extended Search)

Archives APS Brochure Annual Reports Posters Podcasts Image Gallery external site Video Library Syndicated Feeds (RSS) Now Playing: The Advanced Photon Source More videos:...

458

Video Library | Advanced Photon Source  

NLE Websites -- All DOE Office Websites (Extended Search)

Video Library Related Links: APS Colloquium APS Podcasts APS Today More videos: Introduction to the APS Physics of the Blues Now Playing: Building the Advanced Photon Source This...

459

CAT Communicator | Advanced Photon Source  

NLE Websites -- All DOE Office Websites (Extended Search)

Division XSD Groups Industry Argonne Home Advanced Photon Source News Archives CAT Communicator CAT Communicator was a newsletter intended to provide APS information to...

460

Organization Chart | Advanced Photon Source  

NLE Websites -- All DOE Office Websites (Extended Search)

Source (APS) organization comprises three divisions and one project office. Accelerator Systems Division (ASD) ASD provides engineering and physics support for the APS, and...

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


461

Media Center | Advanced Photon Source  

NLE Websites -- All DOE Office Websites (Extended Search)

impact on nearly every aspect of our lives. Annual Reports Articles on Advanced Photon Source research and engineering highlights that are written f