Ikeuchi, Hirotomo; Yano, Kimihiko; Kaji, Naoya; Washiya, Tadahiro [Japan Atomic Energy Agency, 4-33 Muramatsu, Tokai-mura, Ibaraki-ken, 319-1194 (Japan); Kondo, Yoshikazu; Noguchi, Yoshikazu [PESCO Co.Ltd. (Korea, Republic of)
2013-07-01T23:59:59.000Z
For the decommissioning of the Fukushima-Daiichi Nuclear Power Station (1F), the characterization of fuel-debris in cores of Units 1-3 is necessary. In this study, typical phases of the in-vessel fuel-debris were estimated using a thermodynamic equilibrium (TDE) calculation. The FactSage program and NUCLEA database were applied to estimate the phase equilibria of debris. It was confirmed that the TDE calculation using the database can reproduce the phase separation behavior of debris observed in the Three Mile Island accident. In the TDE calculation of 1F, the oxygen potential [G(O{sub 2})] was assumed to be a variable. At low G(O{sub 2}) where metallic zirconium remains, (U,Zr)O{sub 2}, UO{sub 2}, and ZrO{sub 2} were found as oxides, and oxygen-dispersed Zr, Fe{sub 2}(Zr,U), and Fe{sub 3}UZr{sub 2} were found as metals. With an increase in zirconium oxidation, the mass of those metals, especially Fe{sub 3}UZr{sub 2}, decreased, but the other phases of metals hardly changed qualitatively. Consequently, (U,Zr)O{sub 2} is suggested as a typical phase of oxide, and Fe{sub 2}(Zr,U) is suggested as that of metal. However, a more detailed estimation is necessary to consider the distribution of Fe in the reactor pressure vessel through core-melt progression. (authors)
An improved finite difference calculation of downhole dynamometer cards for sucker rod pumps
Everitt, Thomas Aaron
1987-01-01T23:59:59.000Z
AN IMPROVED FINITE DIFFERENCE CALCULATION OF DOWNHOLE DYNAMOMETER CARDS FOR SUCKER ROD PUMPS A Thesis by THOMAS AARON EVERITT Submitted to the Graduate College of Texas A&M University in partial fulfillment of the requirements for the degree... of MASTER OF SCIENCE December 1987 Maj or Subj ect: Petroleum Engineering AN IMPROVED FINITE DIFFERENCE CALCULATION OF DOWNHOLE DYNAMOMETER CARDS FOR SUCKER ROD PUMPS A Thesis by THOMAS AARON EVERITT Approved as to style and content by: James W. nin...
Typical Pure Nonequilibrium Steady States
Takaaki Monnai; Kazuya Yuasa
2014-08-12T23:59:59.000Z
We show that typicality holds for a class of nonequilibrium systems, i.e., nonequilibrium steady states (NESSs): almost all the pure states properly sampled from a certain Hilbert space well represent a NESS and characterize its intrinsic thermal nature. We clarify the relevant Hilbert space from which the pure states are to be sampled, and construct practically all the typical pure NESSs. The scattering approach leads us to the natural extension of the typicality for equilibrium systems. Each pure NESS correctly yields the expectation values of observables given by the standard ensemble approach. It means that we can calculate the expectation values in a NESS with only a single pure NESS. We provide an explicit construction of the typical pure NESS for a model with two reservoirs, and see that it correctly reproduces the Landauer-type formula for the current flowing steadily between the reservoirs.
Effects of the difference in tube voltage of the CT scanner on dose calculation
Rhee, Dong Joo; Moon, Young Min; Kim, Jung Ki; Jeong, Dong Hyeok
2015-01-01T23:59:59.000Z
Computed Tomography (CT) measures the attenuation coefficient of an object and converts the value assigned to each voxel into a CT number. In radiation therapy, CT number, which is directly proportional to the linear attenuation coefficient, is required to be converted to electron density for radiation dose calculation for cancer treatment. However, if various tube voltages were applied to take the patient CT image without applying the specific CT number to electron density conversion curve, the accuracy of dose calculation would be unassured. In this study, changes in CT numbers for different materials due to change in tube voltage were demonstrated and the dose calculation errors in percentage depth dose (PDD) and a clinical case were analyzed. The maximum dose difference in PDD from TPS dose calculation and Monte Carlo simulation were 1.3 % and 1.1 % respectively when applying the same CT number to electron density conversion curve to the 80 kVp and 140 kVp images. In the clinical case, the different CT nu...
Calculation of free-energy differences and potentials of mean force by a multi-energy gap method
Weston, Ken
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
Voloshin, Igor; Karachevtsev, Victor; Zozulya, Victor
2013-01-01T23:59:59.000Z
Binding of acridine derivative quinacrine (QA) to chicken erythrocyte DNA was studied by methods of absorption and polarized fluorescent spectroscopy. Measurements were carried out in aqueous buffered solutions (pH 6.9) of different dye concentrations (QA concentration range from $10^{-6}$ till $10^{-4}$ M) and ionic strengths ($Na^{+}$ concentration rang from $10^{-3}$ till 0.15 M) in a wide range of phosphate-to-dye molar ratios ($P/D$). It is established that the minimum of fluorescent titration curve plotted as relative fluorescence intensity $vs$ $P/D$ is conditioned by the competition between the two types of QA binding to DNA which posses by different emission parameters: (i) intercalative one dominating under high $P/D$ values, and (ii) outside electrostatic binding dominating under low $P/D$ values, which is accompanied by the formation of non-fluorescent dye associates on the DNA backbone. Absorption and fluorescent characteristics of complexes formed were determined. The method of calculation of di...
Calculation of large ion densities under HVdc transmission lines by the finite difference method
Suda, Tomotaka; Sunaga, Yoshitaka [Central Research Institute of Electrical Power Industry, Komae, Tokyo (Japan)] [Central Research Institute of Electrical Power Industry, Komae, Tokyo (Japan)
1995-10-01T23:59:59.000Z
A calculation method for large ion densities (charged aerosols) under HVdc transmission lines was developed considering both the charging mechanism of aerosols by small ions and the drifting process by wind. Large ion densities calculated by this method agreed well with the ones measured under the Shiobara HVdc test line on the lateral profiles at ground level up to about 70m downwind from the line. Measured values decreased more quickly than calculated ones farther downwind from the line. Considering the effect of point discharge from ground cover (earth corona) improved the agreement in the farther downwind region.
Comparison of the calculated neutron noise using finite differences and the Analytical Nodal Method
Demazière, Christophe
noise in the frequency domain via the reactor transfer function using 2-group diffusion theory in 2 Viktor Larsson , Christophe Demazière Chalmers University of Technology, Department of Nuclear: Neutron noise ANM Finite differences 2-group theory a b s t r a c t In this paper, a comparison
Schreiber, Michael
2013-01-01T23:59:59.000Z
Bibliometric indicators can be determined by comparing specific citation records with the percentiles of a reference set. However, there exists an ambiguity in the computation of percentiles because usually a significant number of papers with the same citation count are found at the border between percentile rank classes. The present case study of the citations to the journal Europhysics Letters (EPL) in comparison with all physics papers from the Web of Science shows the deviations which occur due to the different ways of treating the tied papers in the evaluation of the percentage of highly cited publications. A strong bias can occur, if the papers tied at the threshold number of citations are all considered as highly cited or all considered as not highly cited.
Iwase, Shigeru; Ono, Tomoya
2015-01-01T23:59:59.000Z
We propose an efficient procedure to obtain Green's functions by combining the shifted conjugate orthogonal conjugate gradient (shifted COCG) method with the nonequilibrium Green's function (NEGF) method based on a real-space finite-difference (RSFD) approach. The bottleneck of the computation in the NEGF scheme is matrix inversion of the Hamiltonian including the self-energy terms of electrodes to obtain perturbed Green's function in the transition region. This procedure first computes unperturbed Green's functions and calculates perturbed Green's functions from the unperturbed ones using a mathematically strict relation. Since the matrices to be inverted to obtain the unperturbed Green's functions are sparse, complex-symmetric and shifted for a given set of sampling energy points, we can use the shifted COCG method, in which once the Green's function for a reference energy point has been calculated, the Green's functions for the other energy points can be obtained with a moderate computational cost. We calc...
Akkus, Harun, E-mail: physicisthakkus@gmail.com
2013-12-15T23:59:59.000Z
We introduce a method for calculating the amount of deflection angle of light passing close to a massive object. It is based on Fermat’s principle. The varying refractive index of medium around the massive object is obtained from the Buckingham pi-theorem. Highlights: •A different and simpler method for the calculation of deflection angle of light. •Not a curved space, only 2-D Euclidean space. •Getting a varying refractive index from the Buckingham pi-theorem. •Obtaining the some results of general relativity from Fermat’s principle.
Torsnes, I.; Rye, N. (Univ. of Bergen (Norway)); Nesje, A. (Univ. of Bergen, Bergen-Sandviken (Norway))
1993-05-01T23:59:59.000Z
The modern and Little Ice Age (LIA) equilibrium-line altitude (ELA) of 20 outlet valley glacier from Jostedalsbreen, western Norway, has been calculated using different approaches. Using an accumulation area ratio (AAR) of 0.6 [+-] 0.05 gave a mean little Ice Age ELA depression of 70 m. A method developed by M. Kuhle, taking the influence by topography into account gave a mean ELA depression of 35-255 m, the median elevation of glaciers 115 m, and the toe-to-headwall altitude ration 140 m. Differences in the ELA estimates can be attributed to the differences in topography and morphology of the glaciers. The AAR method appears to provide the most reliable results. This will aid in determining mean global temperatures during the LIA. 34 refs., 9 figs., 5 tabs.
charlotb
2014-08-24T23:59:59.000Z
MA 16010 -- CALCULATOR POLICY. A ONE-LINE scientific calculator is REQUIRED. No other calculator is allowed. RECOMMENDED: TI-30Xa calculator
Sandia National Laboratories: composite fibers typically aligned...
Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)
composite fibers typically aligned in a 45 pattern with respect to the blade axis New Material Tests Show Biaxial Laminate Creep Is Important for Large Wind-Turbine Blades On...
Thermal performance of typical light frame walls with reflective surface insulations
Miller, R.G. (Jim Walter Research Corp., St. Petersburg, FL (US)); Riskowski, G.L.; Christianson, L.L. (Agricultural Engineering Dept., Univ. of Illinois at Urbana-Champaign, IL (US))
1989-01-01T23:59:59.000Z
A series of tests were conducted in a guarded hotbox to evaluate the thermal performance (R-value) of wall constructions typical of light-frame buildings that are commonly used in agricultural applications. The systems were insulated with either a commercially available foil-faced bubble pack material (FFBP) or foil-faced polyisocyanurate (PIR) foam board. Tests were conducted under two different temperature conditions, chosen to be representative of a midwestern winter and summer. This paper reports temperatures of the surfaces bounding the reflective airspaces measured and the R-value calculated. These data were used in the ASHRAE series/parallel calculations and the resultant R-value was compared to the measured R-value. Agreement was usually better than 10%.
Robust Neuroimaging-Based Classification Techniques of Autistic vs. Typically
Farag, Aly A.
abnormalities in several brain regions. Increased head size was the first observed characteristic in children1 Robust Neuroimaging-Based Classification Techniques of Autistic vs. Typically Developing Brain with autism. According to the published studies, different anatomical structures of the brain have been
charlotb
2014-06-10T23:59:59.000Z
MA 15800 – Calculators – GOOD AND BAD. ONLY ONE-LINE scientific calculators are permitted. *RECOMMENDED CALCULATOR: TI-30XA(See Below).
charlotb
2014-08-15T23:59:59.000Z
MA 15300 Calculator Policy. ONLY a TI-30Xa scientific calculator is allowed on quizzes and exams. If you have questions, please email the course coordinator ...
charlotb
2014-12-17T23:59:59.000Z
MA 15910 Calculator Policy. ONLY a TI-30Xa scientific calculator is allowed on quizzes and exams. If you have questions, please email the course coordinator ...
Benchmark problems and results for verifying resonance calculation methodologies
Wu, H.; Yang, W.; Qin, Y.; He, L.; Cao, L.; Zheng, Y.; Liu, Q. [NECP Laboratory, School of Nuclear Science and Technology, Xi'An Jiaotong Univ., 710049 (China)
2012-07-01T23:59:59.000Z
Resonance calculation is one of the most important procedures for the multi-group neutron transport calculation. With the development of nuclear reactor concepts, many new types of fuel assembly are raised. Compared to the traditional designs, most of the new fuel assemblies have different fuel types either with complex isotopes or with complicated geometry. This makes the traditional resonance calculation method invalid. Recently, many advanced resonance calculation methods are proposed. However, there are few benchmark problems for evaluating those methods with a comprehensive comparison. In this paper, we design 5 groups of benchmark problems including 21 typical cases of different geometries and fuel contents. The reference results of the benchmark problems are generated based on the sub-group method, ultra-fine group method, function expanding method and Monte Carlo method. It is shown that those benchmark problems and their results could be helpful to evaluate the validity of the newly developed resonance calculation method in the future work. (authors)
Manipulating decision making of typical agents
V. I. Yukalov; D. Sornette
2014-09-02T23:59:59.000Z
We investigate how the choice of decision makers can be varied under the presence of risk and uncertainty. Our analysis is based on the approach we have previously applied to individual decision makers, which we now generalize to the case of decision makers that are members of a society. The approach employs the mathematical techniques that are common in quantum theory, justifying our naming as Quantum Decision Theory. However, we do not assume that decision makers are quantum objects. The techniques of quantum theory are needed only for defining the prospect probabilities taking into account such hidden variables as behavioral biases and other subconscious feelings. The approach describes an agent's choice as a probabilistic event occurring with a probability that is the sum of a utility factor and of an attraction factor. The attraction factor embodies subjective and unconscious dimensions in the mind of the decision maker. We show that the typical aggregate amplitude of the attraction factor is $1/4$, and it can be either positive or negative depending on the relative attraction of the competing choices. The most efficient way of varying the decision makers choice is realized by influencing the attraction factor. This can be done in two ways. One method is to arrange in a special manner the payoff weights, which induces the required changes of the values of attraction factors. We show that a slight variation of the payoff weights can invert the sign of the attraction factors and reverse the decision preferences, even when the prospect utilities remain unchanged. The second method of influencing the decision makers choice is by providing information to decision makers. The methods of influencing decision making are illustrated by several experiments, whose outcomes are compared quantitatively with the predictions of our approach.
Fast Company covers "Just Your Typical New Mexico Image Recognition...
Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)
(Not) just your typical Lab spin off Fast Company covers "Just Your Typical New Mexico Image Recognition Startup Spun Off From A Government Lab" Far from Silicon Valley, Descartes...
McCann, R.A.
1980-12-01T23:59:59.000Z
A finite difference computer code, named HYDRA-I, has been developed to simulate the three-dimensional performance of a spent fuel assembly contained within a cylindrical canister. The code accounts for the coupled heat transfer modes of conduction, convection, and radiation and permits spatially varying boundary conditions, thermophysical properties, and power generation rates. This document is intended as a manual for potential users of HYDRA-I. A brief discussion of the governing equations, the solution technique, and a detailed description of how to set up and execute a problem are presented. HYDRA-I is designed for operation on a CDC 7600 computer. An appendix is included that summarizes approximately two dozen different cases that have been examined. The cases encompass variations in fuel assembly and canister configurations, power generation rates, filler materials, and gases. The results presented show maximum and various local temperatures and heat fluxes illustrating the changing importance of the three heat transfer modes. Finally, the need for comparison with experimental data is emphasized as an aid in code verification although the limited data available indicate excellent agreement.
Pressurized pyrolysis and gasification of Chinese typical coal samples
Hanping Chen; Zhiwu Luo; Haiping Yang; Fudong Ju; Shihong Zhang [Huazhong University of Science and Technology, Wuhan (China). State Key Laboratory of Coal Combustion
2008-03-15T23:59:59.000Z
This paper aims to understand the pyrolysis and gasification behavior of different Chinese coal samples at different pressures. First, the pyrolysis of four typical Chinese coals samples (Xiaolongtan brown coal, Shenfu bituminous coal, Pingzhai anthracite coal, and Heshan lean coal) were carried out using a pressurized thermogravimetric analyzer at ambient pressure and 3 MPa, respectively. The surface structure and elemental component of the resultant char were measured with an automated gas adsorption apparatus and element analyzer. It was observed that higher pressure suppressed the primary pyrolysis, while the secondary pyrolysis of coal particles was promoted. With respect to the resultant solid char, the carbon content increased while H content decreased; however, the pore structure varied greatly with increasing pressure for different coal samples. For Xiaolongtan brown coal (XLT) char, it decreased greatly, while it increased obviously for the other three char types. Then, the isothermal gasification behavior of solid char particles was investigated using an ambient thermal analyzer with CO{sub 2} as the gasifying agent at 1000{sup o}C. The gasification reactivity of solid char was decreased greatly with increasing pyrolysis pressure. However, the extent of change displayed a vital relation with the characteristics of the original coal sample. 26 refs., 5 figs., 5 tabs.
Zhao Dongqiu; Huang Xiaowei; Tian Baoli; Zhou Shaomin; Li Yuncai; Du Zuliang [Key Lab for Special Functional Materials of Ministry of Education, Henan University, Kaifeng 475004 (China)
2011-04-18T23:59:59.000Z
The effect of electronegative difference between nitrogen and oxygen on electronic properties of N-doped anatase TiO{sub 2} has been studied using first-principles calculations. The results indicate that the valence band maximum (VBM) shifts to high energy by 0.27 eV and the band gap states composed of N 2p, O 2p, and Ti 3d states are formed through the three states entering into the gap after N doping. The interactions of three states widen and delocalize the band gap states. The raised VBM and the wide band gap states can improve the visible light photocatalytic activity.
Figure 1. Typical Slow Sand Filter Schematic Supernatant Water
Figure 1. Typical Slow Sand Filter Schematic Headspace Supernatant Water Schmutzdecke Raw water Supernatant drain Filter drain & backfill Sand media Support gravel Drain tile Adjustable weir Overflow weir Vent Control valve Treated Water Effluent flow control structure Overflow Assessing Temperature
andisol typic hapludand: Topics by E-print Network
Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)
from positive to negative from an input range Berns, Hans-Gerd 6 The typical Turing degree CERN Preprints Summary: The Turing degree of a real measures the computational...
Gearbox Typical Failure Modes, Detection, and Mitigation Methods (Presentation)
Sheng, S.
2014-01-01T23:59:59.000Z
This presentation was given at the AWEA Operations & Maintenance and Safety Seminar and focused on what the typical gearbox failure modes are, how to detect them using detection techniques, and strategies that help mitigate these failures.
Structure of The Dixie Valley Geothermal System, a "Typical"...
Dixie Valley Geothermal System, a "Typical" Basin and Range Geothermal System, From Thermal and Gravity Data Jump to: navigation, search OpenEI Reference LibraryAdd to library...
Typical support and Sanov large deviations of correlated states
I. Bjelakovic; J. -D. Deuschel; T. Krueger; R. Seiler; Ra. Siegmund-Schultze; A. Szkola
2007-03-28T23:59:59.000Z
Discrete stationary classical processes as well as quantum lattice states are asymptotically confined to their respective typical support, the exponential growth rate of which is given by the (maximal ergodic) entropy. In the iid case the distinguishability of typical supports can be asymptotically specified by means of the relative entropy, according to Sanov's theorem. We give an extension to the correlated case, referring to the newly introduced class of HP-states.
TYPICAL HOT WATER DRAW PATTERNS BASED ON FIELD DATA
Lutz, Jim; Melody, Moya
2012-11-08T23:59:59.000Z
There is significant variation in hot water use and draw patterns among households. This report describes typical hot water use patterns in single-family residences in North America. We found that daily hot water use is highly variable both among residences and within the same residence. We compared the results of our analysis of the field data to the conditions and draw patterns established in the current U.S. Department of Energy (DOE) test procedure for residential water heaters. The results show a higher number of smaller draws at lower flow rates than used in the test procedure. The data from which the draw patterns were developed were obtained from 12 separate field studies. This report describes the ways in which we managed, cleaned, and analyzed the data and the results of our data analysis. After preparing the data, we used the complete data set to analyze inlet and outlet water temperatures. Then we divided the data into three clusters reflecting house configurations that demonstrated small, medium, or large median daily hot water use. We developed the three clusters partly to reflect efforts of the ASHRAE standard project committee (SPC) 118.2 to revise the test procedure for residential water heaters to incorporate a range of draw patterns. ASHRAE SPC 118.2 has identified the need to separately evaluate at least three, and perhaps as many as five, different water heater capacities. We analyzed the daily hot water use data within each cluster in terms of volume and number of hot water draws. The daily draw patterns in each cluster were characterized using distributions for volume of draws, duration of draws, time since previous draw, and flow rates.
OwenDavis
2014-08-22T23:59:59.000Z
MA 22400 -- CALCULATOR POLICY. A ONE-LINE scientific calculator is REQUIRED. No other calculator is allowed. RECOMMENDED: TI-30Xa calculator
Haselhorst, Alexandria J.
2011-08-08T23:59:59.000Z
or not different foods contain unique bacterial profiles and if there is a correlation between foods and the types of bacteria that may be present. This study was based on diets that are typically consumed by college students. Six meals, two breakfasts, two lunches...
Monte Carlo uncertainty reliability and isotope production calculations for a fast reactor
Miles, T.L.
1992-01-01T23:59:59.000Z
Statistical uncertainties in Monte Carlo calculations are typically determined by the first and second moments of the tally. For certain types of calculations, there is concern that the uncertainty estimate is significantly non-conservative. This is typically seen in reactor eigenvalue problems where the uncertainty estimate is aggravated by the generation-to-generation fission source. It has been speculated that optimization of the random walk, through biasing techniques, may increase the non-conservative nature of the uncertainty estimate. A series of calculations are documented here which quantify the reliability of the Monte Carlo Neutron and Photon (MCNP) mean and uncertainty estimates by comparing these estimates to the true mean. These calculations were made with a liquid metal fast reactor model, but every effort was made to isolate the statistical nature of the uncertainty estimates so that the analysis of the reliability of the MCNP estimates should be relevant for small thermal reactors as well. Also, preliminary reactor physics calculations for two different special isotope production test assemblies for irradiation in the Fast Flux Test Facility (FFTF) were performed using MCNP and are documented here. The effect of an yttrium-hydride moderator to tailor the neutron flux incident on the targets to maximize isotope production for different designs in different locations within the reactor is discussed. These calculations also demonstrate the useful application of MCNP in design iterations by utilizing many of the codes features.
Attenuation of typical sex differences in 800 adults with autism vs. 3,900 controls
Baron-Cohen, Simon; Cassidy, Sarah; Auyeung, Bonnie; Allison, Carrie; Achoukhi, Maryam; Robertson, Sarah; Pohl, Alexa; Lai, Meng-Chuan
2014-07-16T23:59:59.000Z
; Published July 16, 2014 Copyright: #2; 2014 Baron-Cohen et al. This is an open-access article distributed under the terms of the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided... . Most previous studies also suffer from relatively small sample sizes. An exception is the largest study to date using the Simons Simplex Collection, comparing autism symptoms in 304 female and 2,114 male children with ‘simplex’ autism, aged 4–18 years...
Versatile Indian sari: Clothing insulation with different drapes of typical sari ensembles
Indraganti, Madhavi; Lee, Juyoun; Zhang, Hui; Arens, Edward
2014-01-01T23:59:59.000Z
Extension of the Clothing Insulation Database for Standardand air movement on that insulation. , s.l. : s.n. Havenith,Estimation of the thermal insulation and evaporative
Two typical processes ... Isentropic("mechanical" reversible, elastic)
Kostic, Milivoje M.
is coupled and accompanied with energy conversions and dissipation to heat/thermal energy ... Carnot cycle12/28/2011 1 Two typical processes ... · Isentropic("mechanical" reversible, elastic) where useful provides for de-coupling of thermal energy from other types and, YES!, for reversible heat transfer
Energy-Efficient Lighting The typical American family spends more
Energy-Efficient Lighting The typical American family spends more than $1,500 a year on household their energy efficiency is taken into account. CFLs last 810 times longer than standard incandescent bulbs energy bills--and many households spend considerably more. Costs could climb even higher in the future
1 INTRODUCTION A typical flexible pavement system includes four
Zornberg, Jorge G.
1 INTRODUCTION A typical flexible pavement system includes four distinct layers: asphalt concrete course in order to reduce costs or to minimize capil- lary action under the pavement. Figure 1: Cross-section of flexible pavement system (Muench 2006) Pavement distress may occur due to either traffic or environmental
Safety for an Autonomous Bucket Excavator During Typical Landscaping
Berns, Karsten
Safety for an Autonomous Bucket Excavator During Typical Landscaping Tasks Gregor Zolynski, Daniel the goal of automating a mobile bucket excavator for excavation and loading tasks. This document contains a short introduction to the autonomous bucket excavator THOR, a concept for low-level safety using laser
Global variance reduction for Monte Carlo reactor physics calculations
Zhang, Q.; Abdel-Khalik, H. S. [Department of Nuclear Engineering, North Carolina State University, P.O. Box 7909, Raleigh, NC 27695-7909 (United States)
2013-07-01T23:59:59.000Z
Over the past few decades, hybrid Monte-Carlo-Deterministic (MC-DT) techniques have been mostly focusing on the development of techniques primarily with shielding applications in mind, i.e. problems featuring a limited number of responses. This paper focuses on the application of a new hybrid MC-DT technique: the SUBSPACE method, for reactor analysis calculation. The SUBSPACE method is designed to overcome the lack of efficiency that hampers the application of MC methods in routine analysis calculations on the assembly level where typically one needs to execute the flux solver in the order of 10{sup 3}-10{sup 5} times. It places high premium on attaining high computational efficiency for reactor analysis application by identifying and capitalizing on the existing correlations between responses of interest. This paper places particular emphasis on using the SUBSPACE method for preparing homogenized few-group cross section sets on the assembly level for subsequent use in full-core diffusion calculations. A BWR assembly model is employed to calculate homogenized few-group cross sections for different burn-up steps. It is found that using the SUBSPACE method significant speedup can be achieved over the state of the art FW-CADIS method. While the presented speed-up alone is not sufficient to render the MC method competitive with the DT method, we believe this work will become a major step on the way of leveraging the accuracy of MC calculations for assembly calculations. (authors)
Johnson, J.J.; Schewe, E.C.; Maslenikov, O.R.
1984-04-01T23:59:59.000Z
The objectives of this study were two-fold: (1) develop building response calibration factors, i.e., factors which relate best estimate or median level response to responses calculated by selected design procedures. Soil-structure interaction was the phenomenon of interest because significant simplifications are frequently introduced in its treatment; and (2) the second objective can be viewed in the context of a question: what effect does placing an identical structure on different sites and with different foundation conditions have on structure response. The structure selected for this study is a part of the Zion AFT complex. Only the auxiliary, fuel-handling, and diesel generator buildings were studied. This structure is a connected group of shear-wall buildings constructed of reinforced concrete, typical of nuclear power plant structures. The bases of comparison for this study were structure responses: peak in-structure accelerations (27 components), and peak wall forces and moments (111 components). In-structure response spectra were also considered. This appendix contains in-structure response spectra comparisons in detail.
Maximum Photovoltaic Penetration Levels on Typical Distribution Feeders: Preprint
Hoke, A.; Butler, R.; Hambrick, J.; Kroposki, B.
2012-07-01T23:59:59.000Z
This paper presents simulation results for a taxonomy of typical distribution feeders with various levels of photovoltaic (PV) penetration. For each of the 16 feeders simulated, the maximum PV penetration that did not result in steady-state voltage or current violation is presented for several PV location scenarios: clustered near the feeder source, clustered near the midpoint of the feeder, clustered near the end of the feeder, randomly located, and evenly distributed. In addition, the maximum level of PV is presented for single, large PV systems at each location. Maximum PV penetration was determined by requiring that feeder voltages stay within ANSI Range A and that feeder currents stay within the ranges determined by overcurrent protection devices. Simulations were run in GridLAB-D using hourly time steps over a year with randomized load profiles based on utility data and typical meteorological year weather data. For 86% of the cases simulated, maximum PV penetration was at least 30% of peak load.
SSI response of a typical shear wall structure. Volume 1
Johnson, J.J.; Schewe, E.C.; Maslenikov, O.R.
1984-04-01T23:59:59.000Z
The Simplified Methods project of the US NRC-funded Seismic Safety Margins Research Program (SSMRP) has as its goal the development of a methodology to perform routine seismic probabilistic risk assessments of commercial nuclear power plants. The study reported here develops calibration factors to relate best estimate response to design values accounting for approximations and simplifications in SSI analysis procedures. Nineteen cases were analyzed and in-structure response compared. The structure of interest was a typical shear wall structure. 6 references, 44 figures, 22 tables.
Is the Sun Embedded in a Typical Interstellar Cloud?
P. C. Frisch
2008-06-17T23:59:59.000Z
The physical properties and kinematics of the partially ionized interstellar material near the Sun are typical of warm diffuse clouds in the solar vicinity. The interstellar magnetic field at the heliosphere and the kinematics of nearby clouds are naturally explained in terms of the S1 superbubble shell. The interstellar radiation field at the Sun appears to be harder than the field ionizing ambient diffuse gas, which may be a consequence of the low opacity of the tiny cloud surrounding the heliosphere. The spatial context of the Local Bubble is consistent with our location in the Orion spur.
ANALYTICAL APPROACH TO TRANSIENT HEAT CONDUCTION IN COOLING LOAD CALCULATIONS
Michal Duška; Martin Barták; František Drkal; Jan Hensen
equation in cooling load calculations. The performance of nine different procedures (the four methods and
Broader source: Energy.gov [DOE]
Original Impact Calculations, from the Tool Kit Framework: Small Town University Energy Program (STEP).
Optimization Online - Calculating optimal conditions for alloy and ...
Aimen E. Gheribi
2010-12-21T23:59:59.000Z
Dec 21, 2010 ... Calculating optimal conditions for alloy and process design using thermodynamic and property databases, the FactSage software ... is maximized or minimized during annealing or rolling; other calculated functions such as ... which the objectives and constraints are typically outputs of computer simulations.
Radiation Transport Calculations and Simulations
Fasso, Alberto; /SLAC; Ferrari, A.; /CERN
2011-06-30T23:59:59.000Z
This article is an introduction to the Monte Carlo method as used in particle transport. After a description at an elementary level of the mathematical basis of the method, the Boltzmann equation and its physical meaning are presented, followed by Monte Carlo integration and random sampling, and by a general description of the main aspects and components of a typical Monte Carlo particle transport code. In particular, the most common biasing techniques are described, as well as the concepts of estimator and detector. After a discussion of the different types of errors, the issue of Quality Assurance is briefly considered.
Multiphase flow calculation software
Fincke, James R. (Idaho Falls, ID)
2003-04-15T23:59:59.000Z
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.
The SUN Action database : collecting and analyzing typical actions for visual scene types
Olsson, Catherine Anne White
2013-01-01T23:59:59.000Z
Recent work in human and machine vision has increasingly focused on the problem of scene recognition. Scene types are largely defined by the actions one might typically do there: an office is a place someone would typically ...
David, Mathieu; Garde, Francois; Boyer, Harry
2014-01-01T23:59:59.000Z
In building studies dealing about energy efficiency and comfort, simulation software need relevant weather files with optimal time steps. Few tools generate extreme and mean values of simultaneous hourly data including correlation between the climatic parameters. This paper presents the C++ Runeole software based on typical weather sequences analysis. It runs an analysis process of a stochastic continuous multivariable phenomenon with frequencies properties applied to a climatic database. The database analysis associates basic statistics, PCA (Principal Component Analysis) and automatic classifications. Different ways of applying these methods will be presented. All the results are stored in the Runeole internal database that allows an easy selection of weather sequences. The extreme sequences are used for system and building sizing and the mean sequences are used for the determination of the annual cooling loads as proposed by Audrier-Cros (Audrier-Cros, 1984). This weather analysis was tested with the datab...
Some Calculations for Cold Fusion Superheavy Elements
Zhong, X H; Ning, P Z
2004-01-01T23:59:59.000Z
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.
Some Calculations for Cold Fusion Superheavy Elements
X. H. Zhong; L. Li; P. Z. Ning
2004-10-18T23:59:59.000Z
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.
Solar radiation intensity calculations
Levine, Randolph Steven
1978-01-01T23:59:59.000Z
SOLAR RADIATION INTENSITY CALCULATIONS A Thesis by RANDOLPH STEVEN LEVINE Submitted to the Graduate College of Texas A&M University in partia'l fulfillment of the requirement for the degree of MASTER OF SCIENCE December 1978 Major Subject...: Physics SOLAR RADIATION INTENSITY CALCULATIONS A Thesis by RANDOLPH STEVEN LEVINE Approved as to style and content by: (Chairman of Committee) (Member) (Member) ( member) (Head of Department) December 1978 f219 037 ABSTRACT Solar Radiation...
Geothermal Life Cycle Calculator
DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]
Sullivan, John
This calculator is a handy tool for interested parties to estimate two key life cycle metrics, fossil energy consumption (Etot) and greenhouse gas emission (ghgtot) ratios, for geothermal electric power production. It is based solely on data developed by Argonne National Laboratory for DOE’s Geothermal Technologies office. The calculator permits the user to explore the impact of a range of key geothermal power production parameters, including plant capacity, lifetime, capacity factor, geothermal technology, well numbers and depths, field exploration, and others on the two metrics just mentioned. Estimates of variations in the results are also available to the user.
Geothermal Life Cycle Calculator
Sullivan, John
2014-03-11T23:59:59.000Z
This calculator is a handy tool for interested parties to estimate two key life cycle metrics, fossil energy consumption (Etot) and greenhouse gas emission (ghgtot) ratios, for geothermal electric power production. It is based solely on data developed by Argonne National Laboratory for DOE’s Geothermal Technologies office. The calculator permits the user to explore the impact of a range of key geothermal power production parameters, including plant capacity, lifetime, capacity factor, geothermal technology, well numbers and depths, field exploration, and others on the two metrics just mentioned. Estimates of variations in the results are also available to the user.
Abushakra, B.; Haberl, J. S.; Claridge, D. E.
1999-01-01T23:59:59.000Z
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...
Broader source: Energy.gov [DOE]
This calculator estimates the amount of carbon emissions you and members of your household are responsible for. It does not include emissions associated with your work or getting to work if you commute by public transportation. It was developed by IEEE Spectrum magazine.
PROPOSED RESIDENTIAL ALTERNATIVE CALCULATION
PROPOSED RESIDENTIAL ALTERNATIVE CALCULATION MANUAL (ACM) APPROVAL METHOD for the 2013 2012 CEC400201200715DAY #12;201308 Residential ACM Approval Manual 2-2 1. Overview Minimum Modeling Capabilities 1. Overview This Manual explains the requirements for approval of residential Alternative
Finite-difference time-domain calculation of spontaneous
Painter, Oskar
, J. S. Vuckovic´, R. K. Lee, O. J. Painter, A. Scherer, and A. Yariv Departments of Applied Physics
Plutonium 239 Equivalency Calculations
Wen, J
2011-05-31T23:59:59.000Z
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.
Oxygen Toxicity Calculations by Erik C. Baker, P.E.
Read, Charles
1 Oxygen Toxicity Calculations by Erik C. Baker, P.E. Management of exposure to oxygen toxicity myself using the good ole' FORTRAN programming language, I found that incorporating oxygen toxicity for others. Background Two oxygen toxicity parameters are typically "tracked" in technical diving
Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)
AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over Our Instagram Secretary900Steep Slope Calculator Estimates Cooling and Heating
Signal probability calculations using partial functional manipulation
Kodavarti, Ravishankar
1992-01-01T23:59:59.000Z
CALCULATIONS IV THE CUTTING ALGORITHM 14 V RESULTS 17 VI CONCLUSIONS . . REFERENCES APPENDIX A 32 35 LIST OF TABLES TABLE Page I Characteristic table of all ISCAS combinational benchmarks II Number of ambiguous lines using the single best ordering... heuristics can be used to generate orderings, in a few cpu seconds [17]. These heuristics have a very low cost of generation, as compared to that of the best ordering. Iterative OPDD calculations with difFerent variable orderings were made, and the best...
Brain Bases of Reading Fluency in Typical Reading and Impaired Fluency in Dyslexia
Christodoulou, Joanna
Although the neural systems supporting single word reading are well studied, there are limited direct comparisons between typical and dyslexic readers of the neural correlates of reading fluency. Reading fluency deficits ...
Smith, A.
2010-02-16T23:59:59.000Z
Radioactive material package containment vessels typically employ bolted closures of various configurations. Closure bolts must retain the lid of a package and must maintain required seal loads, while subjected to internal pressure, impact loads and vibration. The need for insuring that the specified preload is achieved in closure bolts for radioactive materials packagings has been a continual subject of concern for both designers and regulatory reviewers. The extensive literature on threaded fasteners provides sound guidance on design and torque specification for closure bolts. The literature also shows the uncertainty associated with use of torque to establish preload is typically between 10 and 35%. These studies have been performed under controlled, laboratory conditions. The ability to insure required preload in normal service is, consequently, an important question. The study described here investigated the relationship between indicated torque and resulting bolt load for a typical radioactive materials package closure using methods available under normal service conditions.
Radiation dose estimates for typical piloted NTR lunar and Mars mission engine operations
Schnitzler, B.G. (EG and G Idaho, Inc., Idaho Falls, ID (United States)); Borowski, S.K. (National Aeronautics and Space Administration, Cleveland, OH (United States). Lewis Research Center)
1991-01-01T23:59:59.000Z
The natural and manmade radiation environments to be encountered during lunar and Mars missions are qualitatively summarized. The computational methods available to characterize the radiation environment produced by an operating nuclear propulsion system are discussed. Mission profiles and vehicle configurations are presented for a typical all-propulsive, fully reusable lunar mission and for a typical all-propulsive Mars mission. Estimates of crew location biological doses are developed for all propulsive maneuvers. Post-shutdown dose rates near the nuclear engine are estimated at selected mission times. 15 refs., 4 figs.
Salmon, R.; Hermann, O.W.
1992-10-01T23:59:59.000Z
The rate of neutron production from ([alpha], n) reactions in canisters of immobilized high-level waste containing borosilicate glass or glass-ceramic compositions is significant and must be considered when estimating neutron shielding requirements. The personal computer program ALPHA calculates the ([alpha], n) neutron production rate of a canister of vitrified high-level waste. The user supplies the chemical composition of the glass or glass-ceramic and the curies of the alpha-emitting actinides present. The output of the program gives the ([alpha], n) neutron production of each actinide in neutrons per second and the total for the canister. The ([alpha], n) neutron production rates are source terms only; that is, they are production rates within the glass and do not take into account the shielding effect of the glass. For a given glass composition, the user can calculate up to eight cases simultaneously; these cases are based on the same glass composition but contain different quantities of actinides per canister. In a typical application, these cases might represent the same canister of vitrified high-level waste at eight different decay times. Run time for a typical problem containing 20 chemical species, 24 actinides, and 8 decay times was 35 s on an IBM AT personal computer. Results of an example based on an expected canister composition at the Defense Waste Processing Facility are shown.
Salmon, R.; Hermann, O.W.
1992-10-01T23:59:59.000Z
The rate of neutron production from ({alpha}, n) reactions in canisters of immobilized high-level waste containing borosilicate glass or glass-ceramic compositions is significant and must be considered when estimating neutron shielding requirements. The personal computer program ALPHA calculates the ({alpha}, n) neutron production rate of a canister of vitrified high-level waste. The user supplies the chemical composition of the glass or glass-ceramic and the curies of the alpha-emitting actinides present. The output of the program gives the ({alpha}, n) neutron production of each actinide in neutrons per second and the total for the canister. The ({alpha}, n) neutron production rates are source terms only; that is, they are production rates within the glass and do not take into account the shielding effect of the glass. For a given glass composition, the user can calculate up to eight cases simultaneously; these cases are based on the same glass composition but contain different quantities of actinides per canister. In a typical application, these cases might represent the same canister of vitrified high-level waste at eight different decay times. Run time for a typical problem containing 20 chemical species, 24 actinides, and 8 decay times was 35 s on an IBM AT personal computer. Results of an example based on an expected canister composition at the Defense Waste Processing Facility are shown.
Latkowski, J.F. [Lawrence Livermore National Lab., CA (United States); Sanz, J. [Universidad Politecnica de Madrid (Spain); Vujic, J.L. [California Univ., Berkeley, CA (United States)
1996-06-26T23:59:59.000Z
Inertial fusion energy (IFE) and magnetic fusion energy (MFE) power plants will probably operate in a pulsed mode. The two different schemes, however, will have quite different time periods. Typical repetition rates for IFE power plants will be 1-5 Hz. MFE power plants will ramp up in current for about 1 hour, shut down for several minutes, and repeat the process. Traditionally, activation calculations for IFE and MFE power plants have assumed continuous operation and used either the ``steady state`` (SS) or ``equivalent steady state`` (ESS) approximations. It has been suggested recently that the SS and ESS methods may not yield accurate results for all radionuclides of interest. The present work expands that of Sisolak, et al. by applying their formulae to conditions which might be experienced in typical IFE and MFE power plants. In addition, complicated, multi-step reaction/decay chains are analyzed using an upgraded version of the ACAB radionuclide generation/depletion code. Our results indicate that the SS method is suitable for application to MFE power plant conditions. We also find that the ESS method generates acceptable results for radionuclides with half-lives more than a factor of three greater than the time between pulses. For components that are subject to 0.05 Hz (or more frequent) irradiation (such as coolant), use of the ESS method is recommended. For components or materials that are subject to less frequent irradiation (such as high-Z target materials), pulsed irradiation calculations should be used.
Effects of internal gain assumptions in building energy calculations
Christensen, C.; Perkins, R.
1981-01-01T23:59:59.000Z
The utilization of direct solar gains in buildings can be affected by operating profiles, such as schedules for internal gains, thermostat controls, and ventilation rates. Building energy analysis methods use various assumptions about these profiles. The effects of typical internal gain assumptions in energy calculations are described. Heating and cooling loads from simulations using the DOE 2.1 computer code are compared for various internal-gain inputs: typical hourly profiles, constant average profiles, and zero gain profiles. Prototype single-family-detached and multi-family-attached residential units are studied with various levels of insulation and infiltration. Small detached commercial buildings and attached zones in large commercial buildings are studied with various levels of internal gains. The results of this study indicate that calculations of annual heating and cooling loads are sensitive to internal gains, but in most cases are relatively insensitive to hourly variations in internal gains.
Assessing Student Learning We typically assess student learning in terms of their grades on
Champagne, Frances A.
need to be student-focused rather than instructor-focused. Focus on the learning resulting fromAssessing Student Learning We typically assess student learning in terms of their grades on quizzes should be linked to our learning objectives. To properly assess student learning, you need to know what
Strain Storage Typically, mycobacteria can be stored as lyophilized stocks, agar slants, or frozen stocks. Since lyophilization is not a cost-effective product storage alternative for virulent M. tuberculosis and agar slants can take up considerable BSL3 storage space, the best alternative for strain
Refrigerator: Refrigerators and freezers are not typically constructed to assure that there is no
Cohen, Robert E.
LAB SAFETY Refrigerator: Refrigerators and freezers are not typically constructed to assure temperature of the refrigerator rises. This results in an increase in the concentration of flammable vapors within the refrigerator's interior. When power is restored, a spark generated by the refrigerator light
Fig. 1. Typical topological arrangement of a hybrid fuel cell vehicle drive train [2].
Tolbert, Leon M.
Fig. 1. Typical topological arrangement of a hybrid fuel cell vehicle drive train [2]. TABLE I designed with more robust features. I. INTRODUCTION Fuel cell vehicles (FCV) are widely considered of a hybrid fuel cell vehicle is shown in Fig. 1 [2]. Developments in hybrid automobile industry have
SIR GILBERT WALKER AND A CONNECTION BETWEEN EL NIO AND STATISTICS: FROM "TYPICAL CAMBRIDGE DON" TO
Katz, Richard
autocorrelations (e. g., R statistical programming language) Speech compression #12;11 #12;12 (2) SIR GILBERT Research Boulder, CO USA Home page: www.isse.ucar.edu/staff/katz/ Reference: Katz, R.W. (2002). Statistical1 SIR GILBERT WALKER AND A CONNECTION BETWEEN EL NIÑO AND STATISTICS: FROM "TYPICAL CAMBRIDGE DON
RAMONA-3B calculations for Browns Ferry ATWS (Anticipated Transient Without Scram) study
Saha, P; Slovik, G C; Neymotin, L Y
1987-02-01T23:59:59.000Z
Several aspects of the Anticipated Transient Without Scram (ATWS) initiated by an inadvertent closure of all Main Steam Isolation Valves (MSIV) in a typical BWR/4 are analyzed in the report. The analysis is performed using the Brookhaven National Laboratory code, RAMONA-3B, which employs a three-dimensional neutron kinetics model coupled with a parallel-channel thermal hydraulics in representing a Boiling Water Reactor (BWR) Core. Four different transient scenarios have been investigated: (a) downcomer water level and reactor pressure control, (b) manual control rod insertion transient, (c) high pressure boil-off, and (d) recirculation pump trip failure. Results of these calculations should provide better understanding of mitigative effects of operator actions during ATWS, thus helping in the development of adequate Emergency Procedure Guidelines (EPG) required for the BWR plant safety. A few unresolved questions subject to future investigations are also discussed.
Quantum Monte Carlo calculations for light nuclei
Wiringa, R.B.
1998-08-01T23:59:59.000Z
Quantum Monte Carlo calculations of ground and low-lying excited states for nuclei with A {le} 8 are made using a realistic Hamiltonian that fits NN scattering data. Results for more than 30 different (j{sup {prime}}, T) states, plus isobaric analogs, are obtained and the known excitation spectra are reproduced reasonably well. Various density and momentum distributions and electromagnetic form factors and moments have also been computed. These are the first microscopic calculations that directly produce nuclear shell structure from realistic NN interactions.
A Framework for Lattice QCD Calculations on GPUs
Winter, Frank; Clark, M.A.; Edwards, Robert G.; Joo, Balint
2014-08-01T23:59:59.000Z
Computing platforms equipped with accelerators like GPUs have proven to provide great computational power. However, exploiting such platforms for existing scientific applications is not a trivial task. Current GPU programming frameworks such as CUDA C/C++ require low-level programming from the developer in order to achieve high performance code. As a result porting of applications to GPUs is typically limited to time-dominant algorithms and routines, leaving the remainder not accelerated which can open a serious Amdahl's law issue. The lattice QCD application Chroma allows to explore a different porting strategy. The layered structure of the software architecture logically separates the data-parallel from the application layer. The QCD Data-Parallel software layer provides data types and expressions with stencil-like operations suitable for lattice field theory and Chroma implements algorithms in terms of this high-level interface. Thus by porting the low-level layer one can effectively move the whole application in one swing to a different platform. The QDP-JIT/PTX library, the reimplementation of the low-level layer, provides a framework for lattice QCD calculations for the CUDA architecture. The complete software interface is supported and thus applications can be run unaltered on GPU-based parallel computers. This reimplementation was possible due to the availability of a JIT compiler (part of the NVIDIA Linux kernel driver) which translates an assembly-like language (PTX) to GPU code. The expression template technique is used to build PTX code generators and a software cache manages the GPU memory. This reimplementation allows us to deploy an efficient implementation of the full gauge-generation program with dynamical fermions on large-scale GPU-based machines such as Titan and Blue Waters which accelerates the algorithm by more than an order of magnitude.
A Framework for Lattice QCD Calculations on GPUs
F. T. Winter; M. A. Clark; R. G. Edwards; B. Joó
2014-08-25T23:59:59.000Z
Computing platforms equipped with accelerators like GPUs have proven to provide great computational power. However, exploiting such platforms for existing scientific applications is not a trivial task. Current GPU programming frameworks such as CUDA C/C++ require low-level programming from the developer in order to achieve high performance code. As a result porting of applications to GPUs is typically limited to time-dominant algorithms and routines, leaving the remainder not accelerated which can open a serious Amdahl's law issue. The lattice QCD application Chroma allows to explore a different porting strategy. The layered structure of the software architecture logically separates the data-parallel from the application layer. The QCD Data-Parallel software layer provides data types and expressions with stencil-like operations suitable for lattice field theory and Chroma implements algorithms in terms of this high-level interface. Thus by porting the low-level layer one can effectively move the whole application in one swing to a different platform. The QDP-JIT/PTX library, the reimplementation of the low-level layer, provides a framework for lattice QCD calculations for the CUDA architecture. The complete software interface is supported and thus applications can be run unaltered on GPU-based parallel computers. This reimplementation was possible due to the availability of a JIT compiler (part of the NVIDIA Linux kernel driver) which translates an assembly-like language (PTX) to GPU code. The expression template technique is used to build PTX code generators and a software cache manages the GPU memory. This reimplementation allows us to deploy an efficient implementation of the full gauge-generation program with dynamical fermions on large-scale GPU-based machines such as Titan and Blue Waters which accelerates the algorithm by more than an order of magnitude.
CALCULATING INTERIOR DAYLIGHT ILLUMINATION WITH A PROGRAMMABLE HAND CALCULATOR
Bryan, Harvey J.
2013-01-01T23:59:59.000Z
Committee E-3.2, "Daylight: International RecommendationsCalculation of Natural Daylight," CIE PUBLICATION No. 16,Committee E-3.2, "Natural Daylight: Official Recommenda-
CALCULATING INTERIOR DAYLIGHT ILLUMINATION WITH A PROGRAMMABLE HAND CALCULATOR
Bryan, Harvey J.
2013-01-01T23:59:59.000Z
Committee E-3.2, "Daylight: International Recommendationsthe Calculation of Natural Daylight, 11 CIE PUBLICATION No.Committee E-3.2 1 "Natural Daylight: Official Recommenda-
RTU Comparison Calculator Enhancement Plan
Miller, James D.; Wang, Weimin; Katipamula, Srinivas
2014-03-31T23:59:59.000Z
Over the past two years, Department of Energy’s Building Technologies Office (BTO) has been investigating ways to increase the operating efficiency of the packaged rooftop units (RTUs) in the field. First, by issuing a challenge to the RTU manufactures to increase the integrated energy efficiency ratio (IEER) by 60% over the existing ASHRAE 90.1-2010 standard. Second, by evaluating the performance of an advanced RTU controller that reduces the energy consumption by over 40%. BTO has previously also funded development of a RTU comparison calculator (RTUCC). RTUCC is a web-based tool that provides the user a way to compare energy and cost savings for two units with different efficiencies. However, the RTUCC currently cannot compare savings associated with either the RTU Challenge unit or the advanced RTU controls retrofit. Therefore, BTO has asked PNNL to enhance the tool so building owners can compare energy and savings associated with this new class of products. This document provides the details of the enhancements that are required to support estimating energy savings from use of RTU challenge units or advanced controls on existing RTUs.
Calculation of molecular free energies in classical potentials
Farhi, Asaf
2015-01-01T23:59:59.000Z
Free energy calculations in molecular simulations are used to predict the strength of molecular processes such as binding and solvation. We present an accurate and complete calculation of molecular free energies in standard classical potentials. In this method we transform the molecule by relaxing potential terms that depend on the coordinates of a group of atoms in that molecule and calculate the free energy difference associated with the transformation. Then, since the transformed molecule can be treated as non interacting systems, the free energy associated with these atoms is analytically or numerically calculated. We suggest the potential application of free energy calculation of chemical reactions in classical molecular simulations.
Dose calculations for severe LWR accident scenarios
Margulies, T.S.; Martin, J.A. Jr.
1984-05-01T23:59:59.000Z
This report presents a set of precalculated doses based on a set of postulated accident releases and intended for use in emergency planning and emergency response. Doses were calculated for the PWR (Pressurized Water Reactor) accident categories of the Reactor Safety Study (WASH-1400) using the CRAC (Calculations of Reactor Accident Consequences) code. Whole body and thyroid doses are presented for a selected set of weather cases. For each weather case these calculations were performed for various times and distances including three different dose pathways - cloud (plume) shine, ground shine and inhalation. During an emergency this information can be useful since it is immediately available for projecting offsite radiological doses based on reactor accident sequence information in the absence of plant measurements of emission rates (source terms). It can be used for emergency drill scenario development as well.
LCEs for Naval Reactor Benchmark Calculations
W.J. Anderson
1999-07-19T23:59:59.000Z
The purpose of this engineering calculation is to document the MCNP4B2LV evaluations of Laboratory Critical Experiments (LCEs) performed as part of the Disposal Criticality Analysis Methodology program. LCE evaluations documented in this report were performed for 22 different cases with varied design parameters. Some of these LCEs (10) are documented in existing references (Ref. 7.1 and 7.2), but were re-run for this calculation file using more neutron histories. The objective of this analysis is to quantify the MCNP4B2LV code system's ability to accurately calculate the effective neutron multiplication factor (k{sub eff}) for various critical configurations. These LCE evaluations support the development and validation of the neutronics methodology used for criticality analyses involving Naval reactor spent nuclear fuel in a geologic repository.
Gender stereotypes of typical and ideal man, woman and person: the impact of role inferences
Rhodes, Nancy Deane
1986-01-01T23:59:59.000Z
Housekeeping Mai ntenance of home 1. 40 0. 58 2. 01 0. 82 1. 59 1. 00 0. 225 0. 452 -0. 496 -0. 715 -0. 143 0. 305 9. 19 11. 14 20. 71 22. 76 11. 82 16. 67 4. 38 4. 48 10. 81 7. 71 6. 36 4. 05 7. 09 7. 95 4. 43 2. 76 3. 09 3. 90 Note. Higher numbers... sex, F(2, 121)=3. 23, p&. 05, and target role, F(1, 121)=22. 90, p&. 001. Planned comparisons revealed that the typical man was rated as possessing significantly fewer feminine positive traits than the typical woman, F(1, 121)=6. 53, p&. 01...
An Agricultural Economic Survey of Rockwall County, Texas : A Typical Blackland Cotton Farming Area.
Gabbard, L. P. (Letcher P.)
1925-01-01T23:59:59.000Z
TfXAS AGRICULTURAL fXPfRIMfNT STATION AGRICULTURAL AND MECHANICAL COLLEGE OF TEXAS W. B. BIZZELL, President BULLETIN NO. 327 February, 1925 DIVISION OF FARM AND RANCH ECONOMICS AN AGRICULTURAL ECONOMIC SURVEY OF ROCKWALL COUNTY, TEXAS A... Typical Blackland Cotton Farming Area B. YOUNGBLOOD, DIRECTOR COLLEGE STATION, BRAZOS COUNTY, TEXAS STAFF (As of May 1, 1925) ADMINISTRATION G. N. STROMAN, Ph. D., Agronomist, B. YOUNGBLOOD, M. S., Ph. D., DiTector Cotton Breeding A. B. CONNER, M. S...
Computational Tools for Supersymmetry Calculations
Howard Baer
2009-12-16T23:59:59.000Z
I present a brief overview of a variety of computational tools for supersymmetry calculations, including: spectrum generators, cross section and branching fraction calculators, low energy constraints, general purpose event generators, matrix element event generators, SUSY dark matter codes, parameter extraction codes and Les Houches interface tools.
Calculations of Heat-Capacities of Adsorbates
LAWRENCE, WR; Allen, Roland E.
1976-01-01T23:59:59.000Z
PHYSICAL REVIEW B VOLUME 14, NUMBER 7 1 OCTOBER 1976 Calculations of heat capacities of adsorbates W. R. Lawrence and R. E. Allen Department of Physics, Texas A& M University, College Station, Texas 77843 (Received 2 September 1975) The phonon... the substrate has a perfect (100) surface and the adsorbate goes down as a solid monolayer in registry with the substrate. The quasiharmonic approximation was used, and the results for Ne adsorbates were considerably different from those obtained...
Binding Energies in Benzene Dimers: Nonlocal Density Functional Calculations
Aaron Puzder; Maxime Dion; David C. Langreth
2005-09-15T23:59:59.000Z
The interaction energy and minimum energy structure for different geometries of the benzene dimer has been calculated using the recently developed nonlocal correlation energy functional for calculating dispersion interactions. The comparison of this straightforward and relatively quick density functional based method with recent calculations can elucidate how the former, quicker method might be exploited in larger more complicated biological, organic, aromatic, and even infinite systems such as molecules physisorbed on surfaces, and van der Waals crystals.
Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)
AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office511041clothAdvanced Materials Advanced. C o w l i t z C o . C l a r8.0
SB EE Calculator | Argonne National Laboratory
Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)
Calculator Energy Efficiency Decision Support Calculator Argonne's Energy Efficiency Decision Support Calculator is a simple tool that small business owners can use to quickly...
Guidelines for the analysis of free energy calculations
Klimovich, PV; Shirts, MR; Mobley, DL; Mobley, DL
2015-01-01T23:59:59.000Z
Efficient estimation of free energy differ- ences from Montenumerical instabilities in free energy calculations based onD.L. , DiCapua, F.M. : Free energy via molecular simulation:
Feng, Jingjuan; Bauman, Fred
2013-01-01T23:59:59.000Z
and high temperature cooling_REHVA Guidebook, Federation ofEvaluation of cooling performance of thermally activatedsystem with evaporative cooling source for typical United
Sura, Philip
The construction manager is typically selected at the beginning of the design process. The Guaranteed Maximum Price is usually prepared based on 50% Construction Documents. In these typical cases and 50% Construction Documents. The deliverable at 50% Construction Documents includes the Guaranteed
Burnup calculation methodology in the serpent 2 Monte Carlo code
Leppaenen, J. [VTT Technical Research Centre of Finland, P.O.Box 1000, FI-02044 VTT (Finland); Isotalo, A. [Aalto Univ., Dept. of Applied Physics, P.O.Box 14100, FI-00076 AALTO (Finland)
2012-07-01T23:59:59.000Z
This paper presents two topics related to the burnup calculation capabilities in the Serpent 2 Monte Carlo code: advanced time-integration methods and improved memory management, accomplished by the use of different optimization modes. The development of the introduced methods is an important part of re-writing the Serpent source code, carried out for the purpose of extending the burnup calculation capabilities from 2D assembly-level calculations to large 3D reactor-scale problems. The progress is demonstrated by repeating a PWR test case, originally carried out in 2009 for the validation of the newly-implemented burnup calculation routines in Serpent 1. (authors)
Can electron by Compton scattering be considered as a typical detector of the photon propagation
Vladan Pankovic; Darko Kapor; Miodrag Krmar
2010-06-11T23:59:59.000Z
In this work we consider a possibility that Compton scattering can be considered as a typical measurement (detection) procedure within which electron behaves as the measuring apparatus, i.e. detector (pointer) of the propagation of the photon as the measured object. It represents a realistic variant of the old gendanken (though) experiment (discussed by Einstein, Bohr, Dirac, Feynman) of the interaction between the single photon as the measured object and a movable mirror as the measuring apparatus, i.e. detector (pointer). Here collapse by measurement is successfully modeled by spontaneous (non-dynamical) unitary symmetry (superposition) breaking (effective hiding) representing an especial case of the spontaneous (non-dynamical) breaking (effective hiding) of the dynamical symmetries. All this is full agreement with all existing experimental data and represents the definitive solution of the old problem of "micro" theoretical foundation of measurement or old problem of the foundation of quantum mechanics as a local (luminal) physical theory.
Calculation of Kinetics Parameters for the NBSR
Hanson A. L.; Diamond D.
2012-03-06T23:59:59.000Z
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.
Gräter, Frauke
Protein/Ligand Binding Free Energies Calculated with Quantum Mechanics/Molecular Mechanics Frauke of the complexes are predicted (the "docking" problem) as well as in how the free energy is calculated from)solvation during the binding process.3 Typically, binding free energies calculated with these methods have average
Building wall heat flux calculations
Park, J.E.; Kirkpatrick, J.R.; Tunstall, J.N.; Childs, K.W.
1987-01-01T23:59:59.000Z
Calculations of the heat transfer through the standard stud wall structure of a residential building are described. The wall cavity contains no insulation. Four of the five test cases represent progressively more complicated approximations to the heat transfer through and within a hollow wall structure. The fifth adds the model components necessary to severely inhibit the radiative energy transport across the empty cavity. Flow within the wall cavity is calculated from the Navier-Stokes equations and the energy conservation equation for an ideal gas using the Implicit Compressible Eulerian (ICE) algorithm. The fluid flow calculation is coupled to the radiation-conduction model for the solid portions of the system. Conduction through sill plates is about 4% of the total heat transferred through a composite wall.
Mesh size and code option effects of strength calculations
Kaul, Ann M [Los Alamos National Laboratory
2010-12-10T23:59:59.000Z
Modern Lagrangian hydrodynamics codes include numerical methods which allow calculations to proceed past the point obtainable by a purely Lagrangian scheme. These options can be employed as the user deems necessary to 'complete' a calculation. While one could argue that any calculation is better than none, to truly understand the calculated results and their relationship to physical reality, the user needs to understand how their runtime choices affect the calculated results. One step toward this goal is to understand the effect of each runtime choice on particular pieces of the code physics. This paper will present simulation results for some experiments typically used for strength model validation. Topics to be covered include effect of mesh size, use of various ALE schemes for mesh detangling, and use of anti-hour-glassing schemes. Experiments to be modeled include the lower strain rate ({approx} 10{sup 4} s{sup -1}) gas gun driven Taylor impact experiments and the higher strain rate ({approx} 10{sup 5}-10{sup 6} s{sup -1}) HE products driven perturbed plate experiments. The necessary mesh resolution and the effect of the code runtime options are highly dependent on the amount of localization of strain and stress in each experiment. In turn, this localization is dependent on the geometry of the experimental setup and the drive conditions.
Limitations of the TG-43 formalism for skin high-dose-rate brachytherapy dose calculations
Granero, Domingo, E-mail: dgranero@eresa.com [Department of Radiation Physics, ERESA, Hospital General Universitario, 46014 Valencia (Spain)] [Department of Radiation Physics, ERESA, Hospital General Universitario, 46014 Valencia (Spain); Perez-Calatayud, Jose [Radiotherapy Department, La Fe University and Polytechnic Hospital, Valencia 46026 (Spain)] [Radiotherapy Department, La Fe University and Polytechnic Hospital, Valencia 46026 (Spain); Vijande, Javier [Department of Atomic, Molecular and Nuclear Physics, University of Valencia, Burjassot 46100, Spain and IFIC (UV-CSIC), Paterna 46980 (Spain)] [Department of Atomic, Molecular and Nuclear Physics, University of Valencia, Burjassot 46100, Spain and IFIC (UV-CSIC), Paterna 46980 (Spain); Ballester, Facundo [Department of Atomic, Molecular and Nuclear Physics, University of Valencia, Burjassot 46100 (Spain)] [Department of Atomic, Molecular and Nuclear Physics, University of Valencia, Burjassot 46100 (Spain); Rivard, Mark J. [Department of Radiation Oncology, Tufts University School of Medicine, Boston, Massachusetts 02111 (United States)] [Department of Radiation Oncology, Tufts University School of Medicine, Boston, Massachusetts 02111 (United States)
2014-02-15T23:59:59.000Z
Purpose: In skin high-dose-rate (HDR) brachytherapy, sources are located outside, in contact with, or implanted at some depth below the skin surface. Most treatment planning systems use the TG-43 formalism, which is based on single-source dose superposition within an infinite water medium without accounting for the true geometry in which conditions for scattered radiation are altered by the presence of air. The purpose of this study is to evaluate the dosimetric limitations of the TG-43 formalism in HDR skin brachytherapy and the potential clinical impact. Methods: Dose rate distributions of typical configurations used in skin brachytherapy were obtained: a 5 cm × 5 cm superficial mould; a source inside a catheter located at the skin surface with and without backscatter bolus; and a typical interstitial implant consisting of an HDR source in a catheter located at a depth of 0.5 cm. Commercially available HDR{sup 60}Co and {sup 192}Ir sources and a hypothetical {sup 169}Yb source were considered. The Geant4 Monte Carlo radiation transport code was used to estimate dose rate distributions for the configurations considered. These results were then compared to those obtained with the TG-43 dose calculation formalism. In particular, the influence of adding bolus material over the implant was studied. Results: For a 5 cm × 5 cm{sup 192}Ir superficial mould and 0.5 cm prescription depth, dose differences in comparison to the TG-43 method were about ?3%. When the source was positioned at the skin surface, dose differences were smaller than ?1% for {sup 60}Co and {sup 192}Ir, yet ?3% for {sup 169}Yb. For the interstitial implant, dose differences at the skin surface were ?7% for {sup 60}Co, ?0.6% for {sup 192}Ir, and ?2.5% for {sup 169}Yb. Conclusions: This study indicates the following: (i) for the superficial mould, no bolus is needed; (ii) when the source is in contact with the skin surface, no bolus is needed for either {sup 60}Co and {sup 192}Ir. For lower energy radionuclides like {sup 169}Yb, bolus may be needed; and (iii) for the interstitial case, at least a 0.1 cm bolus is advised for {sup 60}Co to avoid underdosing superficial target layers. For {sup 192}Ir and {sup 169}Yb, no bolus is needed. For those cases where no bolus is needed, its use might be detrimental as the lack of radiation scatter may be beneficial to the patient, although the 2% tolerance for dose calculation accuracy recommended in the AAPM TG-56 report is not fulfilled.
Nucleotide capacitance calculation for DNA sequencing
Lu, Jun-Qiang [ORNL; Zhang, Xiaoguang [ORNL
2008-01-01T23:59:59.000Z
Using a first-principles linear response theory, the capacitance of the DNA nucleotides, adenine, cytosine, guanine and thymine, are calculated. The difference in the capacitance between the nucleotides is studied with respect to conformational distortion. The result suggests that although an alternate current capacitance measurement of a single-stranded DNA chain threaded through a nano-gap electrodes may not sufficient to be used as a stand alone method for rapid DNA sequencing, the capacitance of the nucleotides should be taken into consideration in any GHz-frequency electric measurements and may also serve as an additional criterion for identifying the DNA sequence.
Monte Carlo calculations of nuclei
Pieper, S.C. [Argonne National Lab., IL (United States). Physics Div.
1997-10-01T23:59:59.000Z
Nuclear many-body calculations have the complication of strong spin- and isospin-dependent potentials. In these lectures the author discusses the variational and Green`s function Monte Carlo techniques that have been developed to address this complication, and presents a few results.
Agriculture-related radiation dose calculations
Furr, J.M.; Mayberry, J.J.; Waite, D.A.
1987-10-01T23:59:59.000Z
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.
Typical atmospheric aerosol behavior at the Cherenkov Telescope Array candidate sites in Argentina
Piacentini, Rubén D; Micheletti, María I; Salum, Graciela M; Maya, Javier; Mancilla, Alexis; García, Beatriz
2013-01-01T23:59:59.000Z
Aerosols from natural and antropogenic sources are one of the atmospheric components that have the largest spacial-temporal variability, depending on the type (land or ocean) surface, human activity and climatic conditions (mainly temperature and wind). Since Cherenkov photons generated by the incidence of a primary ultraenergetic cosmic gamma photon have a spectral intensity distribution concentrated in the UV and visible ranges [Hillas AM. Space Science Reviews, 75, 17-30, 1996], it is important to know the aerosol concentration and its contribution to atmospheric radiative transfer. We present results of this concentration measured in typical rather calm (not windy) days at San Antonio de los Cobres (SAC) and El Leoncito/CASLEO proposed Argentinean Andes range sites for the placement of the Cherenkov Telescope Array (CTA). In both places, the aerosol concentration has a peak in the 2.5-5.0$\\mu$m range of the mean aerosol diameter and a very low mean total concentration of 0.097$\\mu$g/m$^3$ (0.365$\\mu$g/m$^...
LBB evaluation for a typical Japanese PWR primary loop by using the US NRC approved methods
Swamy, S.A.; Bhowmick, D.C.; Prager, D.E. [Westinghouse Nuclear Technology Division, Pittsburgh, PA (United States)
1997-04-01T23:59:59.000Z
The regulatory requirements for postulated pipe ruptures have changed significantly since the first nuclear plants were designed. The Leak-Before-Break (LBB) methodology is now accepted as a technically justifiable approach for eliminating postulation of double-ended guillotine breaks (DEGB) in high energy piping systems. The previous pipe rupture design requirements for nuclear power plant applications are responsible for all the numerous and massive pipe whip restraints and jet shields installed for each plant. This results in significant plant congestion, increased labor costs and radiation dosage for normal maintenance and inspection. Also the restraints increase the probability of interference between the piping and supporting structures during plant heatup, thereby potentially impacting overall plant reliability. The LBB approach to eliminate postulating ruptures in high energy piping systems is a significant improvement to former regulatory methodologies, and therefore, the LBB approach to design is gaining worldwide acceptance. However, the methods and criteria for LBB evaluation depend upon the policy of individual country and significant effort continues towards accomplishing uniformity on a global basis. In this paper the historical development of the U.S. LBB criteria will be traced and the results of an LBB evaluation for a typical Japanese PWR primary loop applying U.S. NRC approved methods will be presented. In addition, another approach using the Japanese LBB criteria will be shown and compared with the U.S. criteria. The comparison will be highlighted in this paper with detailed discussion.
Reactivity impact of delayed neutron spectra on MCNP calculations
Mosteller, R.D.; Werner, C.J.
2000-07-01T23:59:59.000Z
The new features in MCNP4C, the latest version of the MCNP Monte Carlo code, include the capability to sample from delayed as well as prompt fission emission spectra. Previous versions of MCNP all have sampled exclusively from prompt spectra. Delayed neutrons typically account for <1% of all neutrons emitted from fission, but the emission spectra for delayed neutrons are somewhat softer than those for prompt neutrons. Because of the softer spectrum, delayed neutrons are less likely to leak from the system, and they also are less likely to cause fission in isotopes that have an effective threshold for fission (e.g., {sup 238}U and {sup 240}Pu). Consequently, the inclusion of delayed neutron spectra can have a small but significant effect on reactivity calculations. This study performs MCNP4C calculations for a series of established benchmarks and quantifies the reactivity impact of the delayed neutron spectra.
Kota, S.; Haberl, J. S.
This paper traces the historical development of different daylighting calculation methods. Over the years there have been several developments in daylighting calculation methods. The last two decades have seen a number of new ideas and approaches...
Sleep and Cortisol in Preschool-Aged Children with Autism and Typically Developing Children
Kidd, Sharon Audrey
2010-01-01T23:59:59.000Z
after administration of 5-HTP, a precursor to serotonin.age berghs, 22 CONT before 5-HTP years of no differences inHealthy teen Belgium (post- HTP volunteers available from
Building wall heat flux calculations
Park, J.E.; Kirkpatrick, J.R.; Tunstall, J.N.; Childs, K.W.
1987-06-01T23:59:59.000Z
Calculations of the heat transfer through the standard stud wall structure of a residential building are described. The wall cavity contains no insulation. Four of the five test cases represent progressively more complicated approximations to the heat transfer through and within a hollow wall structure. The fifth adds the model components necessary to severely inhibit the radiative energy transport across the empty cavity. Flow within the wall cavity is calculated from the Navier-Stokes equations and the energy conservation equation for an ideal gas using the Implicit Compressible Eulerian (ICE) algorithm. The fluid flow calculation is coupled to the radiation-conduction model for the solid portions of the system. Conduction through sill plates is about 4% of the total heat transferred through a composite wall. All of the other model elements (conduction through wall board, sheathing, and siding; convection from siding and wallboard to ambients; and radiation across the wall cavity) are required to accurately predict the heat transfer through a wall. Addition of a foil liner on one inner surface of the wall cavity reduces the total heat transferred by almost 50%.
Jamir, Dewan R.
2006-05-19T23:59:59.000Z
This Field Project provides an overview of the typical substation Engineering-Procurement-Construction (EPC) project delivery method, the work breakdown structure, activities and sequences in the Critical Path Method (CPM) schedule, basic substation...
Gauthier Perron, Sébastien
2012-01-01T23:59:59.000Z
The effects of bend-twist coupling on typical commercial airplane wings are evaluated. An analytical formulation of the orthotropic box beam bending stiffness matrix is derived by combining Euler-Bernoulli beam theory and ...
Lee, Stacey Kirsten
1994-01-01T23:59:59.000Z
to obtain dose rate estimates at several locations near the accelerator. To perform these calculations, simplified computer models were developed from detailed engineering drawings of a typical high-power accelerator design. This research focused on the 20...
Harmonic Analysis Errors in Calculating Dipole,
Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)
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...
Cost Recovery Charge (CRC) Calculation Tables
Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)
Cost Recovery Charge (CRC) Calculation Table Updated: March 20, 2015 FY 2016 February 2015 CRC Calculation Table (pdf) Final FY 2015 CRC Letter & Table (pdf) Note: The Cost...
NERSC Calculations Provide Independent Confirmation of Global...
Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)
Calculations Provide Independent Confirmation of Global Land Warming Since 1901 NERSC Calculations Provide Independent Confirmation of Global Land Warming Since 1901 September 9,...
Boyer, Edmond
; different fishing villages Small-scale fishermen Not really (only extensive fishing methods which do not overexploit the stocks : handline ; encircling gillnet Â« fÃ©lÃ©-fÃ©lÃ© Â» ; beach seine) Fair-Fish, Switzerland of the Sea 2007 World Export : Swiss consumer via Migros supermarket + minimum of fair- fish products
Calculate viscosities for 355 liquids
Yaws, C.L.; Lin, Xiaoyan; Li Bu (Lamar Univ., TX (United States))
1994-04-01T23:59:59.000Z
Liquid viscosities are important factors in process design and operation. The viscosity of a liquid determines its flow properties, such as velocity and pressure drop. In addition, the heat- and mass-transfer characteristics of a liquid are affected by its viscosity. An equation can be used to calculate liquid viscosities as a function of temperature. In the accompanying table, regression coefficients are included for 355 compounds with five, six or seven carbon atoms--generally the most-widely used in the chemical and petroleum industries. To calculate the viscosity of a liquid at any temperature between its melting and critical points (T[sub min] and T[sub max]), use the following equation: log[sub 10] [eta][sub liq] = A + B/T + CT + DT[sup 2] where [eta][sub liq] = viscosity, cP, A,B,C and D = regression coefficients, and T = liquid temperature, K. Insert the temperature into the equation along with the corresponding regression coefficients from the table. The chemical formulae are listed by the number of carbon atoms.
Sensitivity analysis of coupled criticality calculations
Perko, Z.; Kloosterman, J. L.; Lathouwers, D. [Delft Univ. of Technology, Faculty of Applied Physics, Dept. of Radiation, Radionuclides and Reactors, Mekelweg 15, 2629 JB, Delft (Netherlands)
2012-07-01T23:59:59.000Z
Perturbation theory based sensitivity analysis is a vital part of todays' nuclear reactor design. This paper presents an extension of standard techniques to examine coupled criticality problems with mutual feedback between neutronics and an augmenting system (for example thermal-hydraulics). The proposed procedure uses a neutronic and an augmenting adjoint function to efficiently calculate the first order change in responses of interest due to variations of the parameters describing the coupled problem. The effect of the perturbations is considered in two different ways in our study: either a change is allowed in the power level while maintaining criticality (power perturbation) or a change is allowed in the eigenvalue while the power is constrained (eigenvalue perturbation). The calculated response can be the change in the power level, the reactivity worth of the perturbation, or the change in any functional of the flux, the augmenting dependent variables and the input parameters. To obtain power- and criticality-constrained sensitivities power- and k-reset procedures can be applied yielding identical results. Both the theoretical background and an application to a one dimensional slab problem are presented, along with an iterative procedure to compute the necessary adjoint functions using the neutronics and the augmenting codes separately, thus eliminating the need of developing new programs to solve the coupled adjoint problem. (authors)
Calculations of composition boundaries of saturated phases
Brewer, L.; Hahn, S.
1983-09-27T23:59:59.000Z
A program for the HP-41CV calculator is presented for calculating the equilibrium composition boundaries of pairs of saturating solids, liquids, or a combination of a solid and liquid. The activity coefficients must be represented in the form ln ..gamma../sub 1/ = (b/sub h//T - b/sub s/)x/sub 2//sup 2/ + (c/sub h//T - c/sub x/)x/sub 2//sup 3/ where h refers to an enthalpy contribution and s refers to an excess entropy contribution. For solid-liquid equilibria, enthalpies and entropies of fusion are required. For all equilibria, provision is made for use of hypothetical standard states such as the Henry's Law standard states. For example, in treating solid solutions of molybdenum in face-centered cubic metals such as Ni, Rh, or Pt, it is sometimes convenient to use a hypothetical fcc standard state of Mo which represents the limiting Henry's Law behavior of Mo in the fcc metal and has much different properties than a real fcc molybdenum solid.
Electron mobility calculation for graphene on substrates
Hirai, Hideki; Ogawa, Matsuto [Department of Electrical and Electronic Engineering, Graduate School of Engineering, Kobe University, 1-1, Rokko-dai, Nada-ku, Kobe 657-8501 (Japan); Tsuchiya, Hideaki, E-mail: tsuchiya@eedept.kobe-u.ac.jp [Department of Electrical and Electronic Engineering, Graduate School of Engineering, Kobe University, 1-1, Rokko-dai, Nada-ku, Kobe 657-8501 (Japan); Japan Science and Technology Agency, CREST, Chiyoda, Tokyo 102-0075 (Japan); Kamakura, Yoshinari; Mori, Nobuya [Japan Science and Technology Agency, CREST, Chiyoda, Tokyo 102-0075 (Japan); Division of Electrical, Electronic and Information Engineering, Graduate School of Engineering, Osaka University, Suita, Osaka 565-0871 (Japan)
2014-08-28T23:59:59.000Z
By a semiclassical Monte Carlo method, the electron mobility in graphene is calculated for three different substrates: SiO{sub 2}, HfO{sub 2}, and hexagonal boron nitride (h-BN). The calculations account for polar and non-polar surface optical phonon (OP) scatterings induced by the substrates and charged impurity (CI) scattering, in addition to intrinsic phonon scattering in pristine graphene. It is found that HfO{sub 2} is unsuitable as a substrate, because the surface OP scattering of the substrate significantly degrades the electron mobility. The mobility on the SiO{sub 2} and h-BN substrates decreases due to CI scattering. However, the mobility on the h-BN substrate exhibits a high electron mobility of 170?000?cm{sup 2}/(V·s) for electron densities less than 10{sup 12?}cm{sup ?2}. Therefore, h-BN should be an appealing substrate for graphene devices, as confirmed experimentally.
Fung, Jimmy [Los Alamos National Laboratory; Schofield, Sam [LLNL; Shashkov, Mikhail J. [Los Alamos National Laboratory
2012-06-25T23:59:59.000Z
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).
Calculating LHC Tuning Knobs using Various Methods
Wittmer, W; Zimmermann, Frank
2004-01-01T23:59:59.000Z
By measuring and adjusting the beta-functions at the IP the luminosity is being optimized. In LEP this was done with the two closest doublet magnets. This approach is not applicable for the LHC due to the asymmetric lattice and common beam pipe through the triplet magnets. To control and change the beta-functions quadrupole groups situated on both sides further away from the IP have to be used where the two beams are already separated. The quadrupoles are excited in specific linear combinations, forming the socalled “tuning knobs” for the IP beta functions. We compare the performance of such knobs calculated by different methods: (1) matching in MAD, (2) inversion of the response matrix and singular value decomposition inversion and conditioning and (3) conditioning the response matrix by multidimensional minimization using an Adapted Moore Penrose Method.
Numerical calculations of ultrasonic fields. [STEALTH
Johnson, J.A.
1982-02-01T23:59:59.000Z
A code for calculating ultrasonic fields has been developed by revisng the thermal-hydraulics code STEALTH. This code may be used in a wide variety of situations in which a detailed knowledge of a propagating wave field is required. Among the potential used are: interpretation of pulse-echo or pitch-catch ultrasonic signals in complicated geometries; ultrasonic transducer modeling and characterization; optimization and evaluation of transducer design; optimization and reliability of inspection procedures; investigation of the response of different types of reflectors; flaw modeling; and general theoretical acoustics. The code is described, and its limitations and potential are discussed. A discussion of the required input and of the general procedures for running the code is presented. Three sample problems illustrate the input and the use of the code.
Hemmers, Oliver
Career Options for MBA Graduates An MBA graduate typically works in upper management positions with small and large corporations or nonprofit organizations. Managers are needed in all businesses. The type of job often depends on prior work experience and elective courses taken in the MBA program. Popular job
Stern, Robert J.
Glass Inclusions in Mariana Arc Phenocrysts: A New Perspective on Magmatic Evolution in a Typical at Dallas, Box 830688, Richardson, TX 75083-0688, USA A B S T R A C T Major element compositions of glass of these lavas reflects accumulation of plagioclase. Glass inclusions also show the common occurrence of felsic
Cañizares, Claudio A.
Proc. IEEE PowerTech, Bucharest, June 2009. 1 Abstract-Power flow studies are typically used on the use of optimization techniques and worst-case scenario analysis. The application of these techniques assessment), thus allowing to evaluate the level of confidence of power flow studies. These algorithms should
Carter, John
BS in Environmental Science: Typical Program of Study1 Â 4 year (2011 Catalog) Fall Quarter Sciences (5) Core (5)4 ENSC 100Introduction to Environmental Science (2)5 Core (5) Sophomore BIOL) 1 In order to earn a Bachelor of Science in Environmental Science, a student must complete 180
Boyer, Edmond
Simulation of Control Options for HVAC Management of a Typical Office Building. Julien CAILLET thermal comfort and to reduce energy consumption of buildings. Among defect correction, HVAC control appears as a way of significant improvement. HVAC control is examined by using a dynamic simulation
Boyer, Edmond
SIMULATION OF A TYPICAL HOUSE IN THE REGION OF ANTANANARIVO, MADAGASCAR DETERMINATION OF PASSIVE union ABSTRACT This paper deals with new proposals for the design of passive solutions adapted use raw wood to warm the poorly designed houses. This leads to a large scale deforestation
Analysis of drainage and consolidation at typical uranium mill tailings sites
Fayer, M.J.; Conbere, W.
1985-05-01T23:59:59.000Z
The computer code TRUNC was used to analyze three aspects of uranium mill tailings dewatering: the coupling of consolidation and fluid flow, drainage design, and cover load. One-dimensional simulations of the effects of consolidation on fluid flow within a tailings pile of either slimes or a sand/slimes mix showed that drainage flux was greater for a consolidating system early in the simulation. However, after days 1400 and 160 of the simulations for the slimes and sand/slimes mix, respectively, the fluxes from the nonconsolidating systems were greater. In the sand/slimes mix, the nonconsolidating system had a cumulative flux by day 5000 that was 93% of that of the consolidating system. At the same time, in the slimes tailings piles the nonconsolidating system had a cumulative flux of only 34% of that of the consolidating system. This difference indicates that consolidation and fluid flow should not be decoupled for the slimes. Two-dimensional simulations of an actual tailings pile drainage design showed that a sand blanket drain increased the rate of drainage and settlement. The sand blanket drain also significantly reduced differential settlement across the pile. This indicates that the use of a sand blanket drain could enable earlier placement of the cover system after tailings emplacement. In simulations of covered and uncovered tailings piles, nearly the same quantity of water was removed from each, but drainage occurred much more slowly without the cover; hence, surface settlement was slower when the tailings pile was not covered. 10 refs., 19 figs., 2 tabs.
Building Technologies Office: 179D DOE Calculator
Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site
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...
Owen Davis
2013-01-04T23:59:59.000Z
TI-30XA Calculator Tips. Calculator Memory. - To use the memory function, hit the STO key to store a number in either memory 1, 2, or 3. o To store the product of ...
Quantum transport calculations using periodic boundaryconditions
Wang, Lin-Wang
2004-06-15T23:59:59.000Z
An efficient new method is presented to calculate the quantum transports using periodic boundary conditions. This method allows the use of conventional ground state ab initio programs without big changes. The computational effort is only a few times of a normal groundstate calculations, thus is makes accurate quantum transport calculations for large systems possible.
Calculating Evolutionary Dynamics in Structured Populations
Nowak, Martin A.
Calculating Evolutionary Dynamics in Structured Populations Charles G. Nathanson1. , Corina E. Here we provide a general formula for calculating evolutionary dynamics in a wide class of structured) Calculating Evolutionary Dynamics in Structured Populations. PLoS Comput Biol 5(12): e1000615. doi:10
Calculation of size for bound-state constituents
Stanislaw D. Glazek
2014-06-01T23:59:59.000Z
Elements are given of a calculation that identifies the size of a proton in the Schroedinger equation for lepton-proton bound states, using the renormalization group procedure for effective particles (RGPEP) in quantum field theory, executed only up to the second order of expansion in powers of the coupling constant. Already in this crude approximation, the extraction of size of a proton from bound-state observables is found to depend on the lepton mass, so that the smaller the lepton mass the larger the proton size extracted from the same observable bound-state energy splitting. In comparison of Hydrogen and muon-proton bound-state dynamics, the crude calculation suggests that the difference between extracted proton sizes in these two cases can be a few percent. Such values would match the order of magnitude of currently discussed proton-size differences in leptonic atoms. Calculations using the RGPEP of higher order than second are required for a precise interpretation of the energy splittings in terms of the proton size in the Schroedinger equation. Such calculations should resolve the conceptual discrepancy between two conditions: that the renormalization group scale required for high accuracy calculations based on the Schroedinger equation is much smaller than the proton mass (on the order of a root of the product of reduced and average masses of constituents) and that the energy splittings due to the physical proton size can be interpreted ignoring corrections due to the effective nature of constituents in the Schr\\"odinger equation.
ESTIMATING THE UNCERTAINTY IN REACTIVITY ACCIDENT NEUTRONIC CALCULATIONS
DIAMOND,D.J.; YANG,C.Y.; ARONSON,A.L.
1998-10-26T23:59:59.000Z
A study of the uncertainty in calculations of the rod ejection accident in a pressurized water reactor is being carried out for the US Nuclear Regulatory Commission. This paper is a progress report on that study. Results are presented for the sensitivity of core energy deposition to the key parameters: ejected rod worth, delayed neutron fraction, Doppler reactivity coefficient, and fuel specific heat. These results can be used in the future to estimate the uncertainty in local fuel enthalpy given some assumptions about the uncertainty in the key parameters. This study is also concerned with the effect of the intra-assembly representation in calculations. The issue is the error that might be present if assembly-average power is calculated, and pin peaking factors from a static calculation are then used to determine local fuel enthalpy. This is being studied with the help of a collaborative effort with Russian and French analysts who are using codes with different intra-assembly representations. The US code being used is PARCS which calculates power on an assembly-average basis. The Russian code being used is BARS which calculates power for individual fuel pins using a heterogeneous representation based on a Green's Function method.
Estimating the uncertainty in reactivity accident neutronic calculations
Diamond, D.J.; Yang, C.Y.; Aronson, A.L.
1998-12-31T23:59:59.000Z
A study of the uncertainty in calculations of the rod ejection accident in a pressurized water reactor is being carried out for the US Nuclear Regulatory Commission. This paper is a progress report on that study. Results are presented for the sensitivity of core energy deposition to the key parameters: ejected rod worth, delayed neutron fraction, Doppler reactivity coefficient, and fuel specific heat. These results can be used in the future to estimate the uncertainty in local fuel enthalpy given some assumptions about the uncertainty in the key parameters. This study is also concerned with the effect of the intra-assembly representation in calculations. The issue is the error that might be present if assembly-average power is calculated, and pin peaking factors from a static calculation are then used to determine local fuel enthalpy. This is being studied with the help of a collaborative effort with Russian and French analysts who are using codes with different intra-assembly representations. The US code being used is PARCS which calculates power on an assembly-average basis. The Russian code being used is BARS which calculates power for individual fuel pins using a heterogeneous representation based on a Green`s Function method.
Koner, Debasish; Panda, Aditya N., E-mail: adi07@iitg.ernet.in [Department of Chemistry, Indian Institute of Technology Guwahati, Guwahati 781039 (India); Barrios, Lizandra; González-Lezana, Tomás, E-mail: t.gonzalez.lezana@csic.es [Instituto de Física Fundamental, C.S.I.C., Serrano 123, Madrid 28006 (Spain)
2014-09-21T23:59:59.000Z
A real wave packet based time-dependent method and a statistical quantum method have been used to study the He + NeH{sup +} (v, j) reaction with the reactant in various ro-vibrational states, on a recently calculated ab initio ground state potential energy surface. Both the wave packet and statistical quantum calculations were carried out within the centrifugal sudden approximation as well as using the exact Hamiltonian. Quantum reaction probabilities exhibit dense oscillatory pattern for smaller total angular momentum values, which is a signature of resonances in a complex forming mechanism for the title reaction. Significant differences, found between exact and approximate quantum reaction cross sections, highlight the importance of inclusion of Coriolis coupling in the calculations. Statistical results are in fairly good agreement with the exact quantum results, for ground ro-vibrational states of the reactant. Vibrational excitation greatly enhances the reaction cross sections, whereas rotational excitation has relatively small effect on the reaction. The nature of the reaction cross section curves is dependent on the initial vibrational state of the reactant and is typical of a late barrier type potential energy profile.
Petty, J. A.; Lacewell, R. D.; Hardin, D. C.; Whitson, R. E.
and new technology. The model includes a Fortran sub-routine that adjusts irrigation factors each year based on the linear programming solution of the previous year. After calculating new pumping energy requirements, well yield, and pumping lift...
Identifying and bounding uncertainties in nuclear reactor thermal power calculations
Phillips, J.; Hauser, E.; Estrada, H. [Cameron, 1000 McClaren Woods Drive, Coraopolis, PA 15108 (United States)
2012-07-01T23:59:59.000Z
Determination of the thermal power generated in the reactor core of a nuclear power plant is a critical element in the safe and economic operation of the plant. Direct measurement of the reactor core thermal power is made using neutron flux instrumentation; however, this instrumentation requires frequent calibration due to changes in the measured flux caused by fuel burn-up, flux pattern changes, and instrumentation drift. To calibrate the nuclear instruments, steam plant calorimetry, a process of performing a heat balance around the nuclear steam supply system, is used. There are four basic elements involved in the calculation of thermal power based on steam plant calorimetry: The mass flow of the feedwater from the power conversion system, the specific enthalpy of that feedwater, the specific enthalpy of the steam delivered to the power conversion system, and other cycle gains and losses. Of these elements, the accuracy of the feedwater mass flow and the feedwater enthalpy, as determined from its temperature and pressure, are typically the largest contributors to the calorimetric calculation uncertainty. Historically, plants have been required to include a margin of 2% in the calculation of the reactor thermal power for the licensed maximum plant output to account for instrumentation uncertainty. The margin is intended to ensure a cushion between operating power and the power for which safety analyses are performed. Use of approved chordal ultrasonic transit-time technology to make the feedwater flow and temperature measurements (in place of traditional differential-pressure- based instruments and resistance temperature detectors [RTDs]) allows for nuclear plant thermal power calculations accurate to 0.3%-0.4% of plant rated power. This improvement in measurement accuracy has allowed many plant operators in the U.S. and around the world to increase plant power output through Measurement Uncertainty Recapture (MUR) up-rates of up to 1.7% of rated power, while also decreasing the probability of significant over-power events. This paper will examine the basic elements involved in calculation of thermal power using ultrasonic transit-time technology and will discuss the criteria for bounding uncertainties associated with each element in order to achieve reactor thermal power calculations to within 0.3% to 0.4%. (authors)
Recent PQCD calculations of heavy quark production
Vitev, I
2006-01-01T23:59:59.000Z
We summarize the results of a recent study of heavy quark production and attenuation in cold nuclear matter. In p+p collisions, we investigate the relative contribution of partonic sub-processes to $D$ meson production and $D$ meson-triggered inclusive di-hadrons to lowest order in perturbative QCD. While gluon fusion dominates the creation of large angle $D\\bar{D}$ pairs, charm on light parton scattering determines the yield of single inclusive $D$ mesons. The distinctly different non-perturbative fragmentation of $c$ quarks into $D$ mesons versus the fragmentation of quarks and gluons into light hadrons results in a strong transverse momentum dependence of anticharm content of the away-side charm-triggered jet. In p+A reactions, we calculate and resum the coherent nuclear-enhanced power corrections from the final-state partonic scattering in the medium. We find that single and double inclusive open charm production can be suppressed as much as the yield of neutral pions from dynamical high-twist shadowing. ...
Visual Analytics for Roof Savings Calculator Ensembles
Jones, Chad [University of California, Davis] [University of California, Davis; New, Joshua Ryan [ORNL] [ORNL; Sanyal, Jibonananda [ORNL] [ORNL; Ma, Kwan-Liu [University of California, Davis] [University of California, Davis
2012-01-01T23:59:59.000Z
The Roof Savings Calculator (RSC) has been deployed for DOE as an industry-consensus, web-based tool for easily running complex building energy simulations. These simulations allow both homeowners and experts to determine building-specific cost and energy savings for modern roof and attic technologies. Using a database of over 3 million RSC simulations for different combinations of parameters, we have built a visual analytics tool to assist in the exploration and identification of features in the data. Since the database contains multiple variables, both categorical and continuous, we employ a coordinated multi-view approach that allows coordinated feature exploration through multiple visualizations at once. The main component of our system, a parallel coordinates view, has been adapted to handle large-scale, mixed data types as are found in RSC simulations. Other visualizations include map coordinated plots, high dynamic range (HDR) line plot rendering, and an intuitive user interface. We demonstrate these techniques with several use cases that have helped identify software and parametric simulation issues.
Monte Carlo reactor calculation with substantially reduced number of cycles
Lee, M. J.; Joo, H. G. [Seoul National Univ., 599 Gwanak-ro, Gwanak-gu, Seoul, 151-744 (Korea, Republic of); Lee, D. [Ulsan National Inst. of Science and Technology, UNIST-gil 50, Eonyang-eup, Ulju-gun, Ulsan, 689-798 (Korea, Republic of); Smith, K. [Massachusetts Inst. of Technology, 77 Massachusetts Avenue, Cambridge, MA 02139-4307 (United States)
2012-07-01T23:59:59.000Z
A new Monte Carlo (MC) eigenvalue calculation scheme that substantially reduces the number of cycles is introduced with the aid of coarse mesh finite difference (CMFD) formulation. First, it is confirmed in terms of pin power errors that using extremely many particles resulting in short active cycles is beneficial even in the conventional MC scheme although wasted operations in inactive cycles cannot be reduced with more particles. A CMFD-assisted MC scheme is introduced as an effort to reduce the number of inactive cycles and the fast convergence behavior and reduced inter-cycle effect of the CMFD assisted MC calculation is investigated in detail. As a practical means of providing a good initial fission source distribution, an assembly based few-group condensation and homogenization scheme is introduced and it is shown that efficient MC eigenvalue calculations with fewer than 20 total cycles (including inactive cycles) are possible for large power reactor problems. (authors)
Fully microscopic shell-model calculations with realistic effective hamiltonians
L. Coraggio; A. Covello; A. Gargano; N. Itaco; T. T. S. Kuo
2011-01-24T23:59:59.000Z
The advent of nucleon-nucleon potentials derived from chiral perturbation theory, as well as the so-called V-low-k approach to the renormalization of the strong short-range repulsion contained in the potentials, have brought renewed interest in realistic shell-model calculations. Here we focus on calculations where a fully microscopic approach is adopted. No phenomenological input is needed in these calculations, because single-particle energies, matrix elements of the two-body interaction, and matrix elements of the electromagnetic multipole operators are derived theoretically. This has been done within the framework of the time-dependent degenerate linked-diagram perturbation theory. We present results for some nuclei in different mass regions. These evidence the ability of realistic effective hamiltonians to provide an accurate description of nuclear structure properties.
Review of Axial Burnup Distribution Considerations for Burnup Credit Calculations
Wagner, J.C.; DeHart, M.D.
2000-03-01T23:59:59.000Z
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.
Theory and calculations of synchrotron instabilities and feedback-mechanism
Meijssen, T.E.M.
1981-08-12T23:59:59.000Z
The properties of the phenomenon synchrotron radiation are given with general theory on the basic processes and betatron and synchrotron oscillations. A more extended theoretical view at transverse instabilities and the influence of a damping feedback system are discussed. The longitudinal case is covered. For the calculations on the longitudinal case with M equally spaced pointbunches, with N electrons each, in the storage ring, the parasitic modes of the radio-frequency cavity were measured. A description of this is given. The values of damping rates of the longitudinal feedback system found, are as expected, but too low to damp the longitudinal instabilities calculated. This might be caused by the input data. The calculated growth rates are very sensitive to changes in frequency and width of the parasitic modes, which were measured under conditions differing slightly from the operating conditions.
Fully microscopic shell-model calculations with realistic effective hamiltonians
Coraggio, L; Gargano, A; Itaco, N; Kuo, T T S
2011-01-01T23:59:59.000Z
The advent of nucleon-nucleon potentials derived from chiral perturbation theory, as well as the so-called V-low-k approach to the renormalization of the strong short-range repulsion contained in the potentials, have brought renewed interest in realistic shell-model calculations. Here we focus on calculations where a fully microscopic approach is adopted. No phenomenological input is needed in these calculations, because single-particle energies, matrix elements of the two-body interaction, and matrix elements of the electromagnetic multipole operators are derived theoretically. This has been done within the framework of the time-dependent degenerate linked-diagram perturbation theory. We present results for some nuclei in different mass regions. These evidence the ability of realistic effective hamiltonians to provide an accurate description of nuclear structure properties.
Shao, Hongbo; Thompson, Christopher J.; Cantrell, Kirk J.
2013-11-01T23:59:59.000Z
pH is an essential parameter for understanding the geochemical reactions that occur in rock-brine-CO2 systems when CO2 is injected into deep geologic formations for long-term storage. Due to a lack of reliable experimental methods, most laboratory studies conducted under geological CO2 sequestration (GCS) conditions have relied on thermodynamic modeling to estimate pH. The accuracy of these model predictions is typically uncertain. In our previous work, we have developed a method for pH determination by in-situ spectrophotometry. In the present work, we expanded the applicable pH range for this method and measured the pH of several rock-brine-CO2 systems at GCS conditions for five rock samples collected from ongoing GCS demonstration projects. Experimental measurements were compared with pH values calculated using several geochemical modeling approaches. The effect of different thermodynamic databases on the accuracy of model prediction was evaluated. Results indicate that the accuracy of model calculations is rock-dependent. For rocks comprised of carbonate and sandstone, model results generally agreed well with experimentally measured pH; however, for basalt, significant differences were observed. These discrepancies may be due to the models’ failure to fully account for certain reaction occurring between the basalt minerals the CO2-saturated brine solutions.
What is the GREET Fleet Footprint Calculator
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...
Cooling airflow design calculations for UFAD
Bauman, Fred; Webster, Tom; Benedek, Corinne
2007-01-01T23:59:59.000Z
written permission. Cooling Airflow Design Calculations form) height. Table 2: Design cooling airflow performance fortool predictions of UFAD cooling airflow rates and associ-
Calculators and Science and Engineering Calculus Occasionally ...
1910-10-51T23:59:59.000Z
on examinations and quizzes. These courses do spend some class time discussing the use of graphing calculators, and some of the pitfalls into which graphing ...
Evaluation Of Chemical Geothermometers For Calculating Reservoir...
For Calculating Reservoir Temperatures At Nevada Geothermal Power Plants Jump to: navigation, search OpenEI Reference LibraryAdd to library Conference Paper: Evaluation Of Chemical...
Filter diagonalization of shell-model calculations
Mizusaki, Takahiro [Institute of Natural Sciences, Senshu University, Tokyo 101-8425 (Japan); Kaneko, Kazunari [Department of Physics, Kyushu Sangyo University, Fukuoka 813-8503 (Japan); Honma, Michio [Center for Mathematical Sciences, University of Aizu, Aizu-Wakamatsu, 965-8580 (Japan); Sakurai, Tetsuya [Department of Computer Science, University of Tsukuba, Tsukuba, 305-8573 (Japan)
2010-08-15T23:59:59.000Z
We present a method of filter diagonalization for shell-model calculations. This method is based on the Sakurai and Sugiura (SS) method, but extended with the help of the shifted complex orthogonal conjugate gradient (COCG) method. A salient feature of this method is that it can calculate eigenvalues and eigenstates in a given energy interval. We show that this method can be an alternative to the Lanczos method for calculating ground and excited states, as well as spectral strength functions. With an application to the M-scheme shell-model calculations we demonstrate that several inherent problems in the widely used Lanczos method can be removed or reduced.
SPREADSHEET DESCRIPTION DOCUMENT FOR SATURATION TEMPERATURE CALCULATION
JO J
2008-08-29T23:59:59.000Z
This document describes the methodology for determining the saturation temperature in waste tanks. The saturation temperature is used to calculate neutral buoyancy ratio.
Calculating Plutonium and Praseodymium Structural Transformations...
Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)
Calculating Plutonium and Praseodymium Structural Transformations A newly-developed hybrid computational method has computed, for the first time, plutonium's exotic crystal...
Born-series approach to the calculation of Casimir forces
Robert Bennett
2014-07-01T23:59:59.000Z
The Casimir force between two objects is notoriously difficult to calculate in anything other than parallel-plate geometries due to its non-additive nature. This means that for more complicated, realistic geometries one usually has to resort to approaches such as making the crude proximity force approximation (PFA). Another issue with calculation of Casimir forces in real-world situations (such as with realistic materials) is that there are continuing doubts about the status of the standard Lifshitz treatment as a true quantum theory. Here we demonstrate an alternative approach to calculation of Casimir forces for arbitrary geometries which sidesteps both these problems. Our calculations are based upon a Born expansion of the Green's function of the quantised electromagnetic vacuum field, interpreted as multiple scattering, with the relevant coupling strength being the difference in the dielectric functions of the various materials involved. This allows one to consider arbitrary geometries in single or multiple scattering simply by integrating over the desired shape, meaning that extension beyond the PFA is trivial. This work is mostly dedicated to illustration of the method by reproduction of known parallel-slab results -- a process that turns out to be non-trivial and provides several useful insights. We also present a short example of calculation of the Casimir energy for a more complicated geometry, namely that of two finite slabs.
Hamp, S. [USDOE Albuquerque Operations Office, NM (United States). Uranium Mill Tailings Remedial Action Project Office; Jackson, T.J. [Geraghty and Miller, Inc., Albuquerque, NM (United States); Dotson, P.W. [Roy F. Weston, Inc., Albuquerque, NM (United States)
1995-03-01T23:59:59.000Z
Past operations at uranium processing sites throughout the US have resulted in local contamination of soils and ground water by radionuclides, toxic metals, or both. Understanding the origin of contamination and how the constituents are distributed is a basic element for planning remedial action decisions. This report describes the radiological and nonradiological species found in ground water at a typical US uranium milling facility. The report will provide the audience with an understanding of the vast spectrum of contaminants that must be controlled in planning solutions to the long-term management of these waste materials.
Multipole Electrostatics in Hydration Free Energy Calculations
Ponder, Jay
Multipole Electrostatics in Hydration Free Energy Calculations YUE SHI,1 CHUANJIE WU,2 JAY W Acceptance Ratio method. We have compared two approaches to derive the atomic multipoles from quantum mechanical calculations: one directly from the new distributed multipole analysis and the other involving
Calculating Highly Oscillatory Integrals by Quadrature Methods
Thapa, Krishna 1989-
2012-04-24T23:59:59.000Z
are found by requiring Z b a m (x) sin(!x)dx = 2 +2X i= wim (xi) The calculation of the wi therefore hinges on calculating the moments R b a x nei!g(x)dx. Unlike traditional approximation methods, the accuracy of the function increases...
PVWatts (R) Calculator India (Fact Sheet)
Not Available
2014-01-01T23:59:59.000Z
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.
First principles calculations for analysis martensitic transformations
Harmon, B.N.; Zhao, G.L.; Ho, K.M.; Chan, C.T.; Ye, Y.Y.; Ding, Y.; Zhang, B.L.
1993-10-01T23:59:59.000Z
The change in crystal energy is calculated for atomic displacements corresponding to phonons, elastic shears, and lattice transformations. Anomalies in the phonon dispersion curves of NiAl and NiTi are analyzed and recent calculations for TiPd alloys are presented.
URANIUM MILL TAILINGS RADON FLUX CALCULATIONS
URANIUM MILL TAILINGS RADON FLUX CALCULATIONS PIÃ?ON RIDGE PROJECT MONTROSE COUNTY, COLORADO Inc. (Golder) was commissioned by EFRC to evaluate the operations of the uranium mill tailings storage in this report were conducted using the WISE Uranium Mill Tailings Radon Flux Calculator, as updated on November
Quark model calculation of the EMC effect
Benesh, C.J.; Goldman, T.; Stephenson, G.J. Jr. [Los Alamos National Laboratory, NM (United States)
1993-10-01T23:59:59.000Z
Using a potential model, we calculate quark distributions for a six-quark quasi-deuteron, including the effects of the Pauli Principle and quark tunneling between nuclei. Using a phenomenological sea distribution, the EMC ratio is calculated and found to be in qualitative agreement with experiment.
AUXILIARY RATE CALCULATION The Budget Office
Weston, Ken
AUXILIARY RATE CALCULATION The Budget Office #12;AGENDA Guiding Principles Rate Proposal Building Office supplies for budget manager reconciliationOffice supplies for budget manager reconciliation: Equipment Compensated Leave #12;CALCULATING A RATE Budgeted Expenses Budgeted Usage BaseBudgeted Usage Base
Krylov, Anna I.
Efficient Strategies for Accurate Calculations of Electronic Excitation and Ionization Energies on single-reference methods for calculating accurate energy differences. Different schemes for calculating of energy differences, such as electronic excitation and ionization energies, as well as heats of formation
Relativistic QRPA calculation of muon capture rates
T. Marketin; N. Paar; T. Niksic; D. Vretenar
2009-03-30T23:59:59.000Z
The relativistic proton-neutron quasiparticle random phase approximation (PN-RQRPA) is applied in the calculation of total muon capture rates on a large set of nuclei from $^{12}$C to $^{244}$Pu, for which experimental values are available. The microscopic theoretical framework is based on the Relativistic Hartree-Bogoliubov (RHB) model for the nuclear ground state, and transitions to excited states are calculated using the PN-RQRPA. The calculation is fully consistent, i.e., the same interactions are used both in the RHB equations that determine the quasiparticle basis, and in the matrix equations of the PN-RQRPA. The calculated capture rates are sensitive to the in-medium quenching of the axial-vector coupling constant. By reducing this constant from its free-nucleon value $g_A = 1.262$ by 10% for all multipole transitions, the calculation reproduces the experimental muon capture rates to better than 10% accuracy.
Francetic, J.S.; Robinson, K.S.
1987-07-01T23:59:59.000Z
Recent comprehensive monitoring of solar energy systems has indicated that heat losses from system piping and components are much higher than originally expected. Theoretical analyses conducted at the Energy Technology Engineering Center (ETEC) predict that operating plus standby (during shutdown) heat losses from a typical solar system could equal up to one-third of the total gross solar energy collected by the system. Detailed heat loss experiments were conducted on a Solar in Federal Buildings Program (SFBP)-monitored site to identify and quantify actual piping, component, and thermosiphon heat losses for a typical day. The selected solar system, SFBP 4008, is a solar space heating and domestic hot water (DHW) system located at the Eisenhower Memorial Museum at Abilene, Kansas. The system has 4200 ft/sup 2/ of collector array located at a considerable distance from the mechanical building. Long lengths of exterior above-ground and buried piping connect the collectors to the mechanical room. Valves and pumps are uninsulated. The heat loss experiments at the Eisenhower site showed that 25% of the energy collected on a summer day was lost in pipes and components. Detailed results are given. 8 refs., 64 figs., 17 tabs.
Scheib, J.; Pless, S.; Torcellini, P.
2014-08-01T23:59:59.000Z
NREL experienced a significant increase in employees and facilities on our 327-acre main campus in Golden, Colorado over the past five years. To support this growth, researchers developed and demonstrated a new building acquisition method that successfully integrates energy efficiency requirements into the design-build requests for proposals and contracts. We piloted this energy performance based design-build process with our first new construction project in 2008. We have since replicated and evolved the process for large office buildings, a smart grid research laboratory, a supercomputer, a parking structure, and a cafeteria. Each project incorporated aggressive efficiency strategies using contractual energy use requirements in the design-build contracts, all on typical construction budgets. We have found that when energy efficiency is a core project requirement as defined at the beginning of a project, innovative design-build teams can integrate the most cost effective and high performance efficiency strategies on typical construction budgets. When the design-build contract includes measurable energy requirements and is set up to incentivize design-build teams to focus on achieving high performance in actual operations, owners can now expect their facilities to perform. As NREL completed the new construction in 2013, we have documented our best practices in training materials and a how-to guide so that other owners and owner's representatives can replicate our successes and learn from our experiences in attaining market viable, world-class energy performance in the built environment.
Experiences with leak rate calculations methods for LBB application
Grebner, H.; Kastner, W.; Hoefler, A.; Maussner, G. [and others
1997-04-01T23:59:59.000Z
In this paper, three leak rate computer programs for the application of leak before break analysis are described and compared. The programs are compared to each other and to results of an HDR Reactor experiment and two real crack cases. The programs analyzed are PIPELEAK, FLORA, and PICEP. Generally, the different leak rate models are in agreement. To obtain reasonable agreement between measured and calculated leak rates, it was necessary to also use data from detailed crack investigations.
Statistical verification of neutron-physics programs for calculations in support of nuclear safety
Tebin, V. V., E-mail: tebin@vver.kiae.ru [Russian Research Centre Kurchatov Institute (Russian Federation)
2012-12-15T23:59:59.000Z
An algorithm for statistical verification of the XT26 code contained in the SAPHIRE-2006 code system is described. The results of conservative estimation of the calculation error in the K{sub eff} calculations for different types of benchmark experiments are presented. The results of the statistical analysis of deviations from the experimental values are compared with the corresponding parameters obtained from the set of calculations performed using other codes.
Yerokhin, V A; Fritzsche, S
2014-01-01T23:59:59.000Z
Relativistic configuration-interaction calculations have been performed for the energy levels of the low-lying and core-excited states of beryllium-like argon, Ar$^{14+}$. These calculations include the one-loop QED effects as obtained by two different methods, the screening-potential approach as well as the model QED operator approach. The calculations are supplemented by a systematic estimation of uncertainties of theoretical predictions.
Project W-320, 241-C-106 sluicing: Piping calculations. Volume 4
Bailey, J.W.
1998-07-24T23:59:59.000Z
This supporting document has been prepared to make the FDNW calculations for Project W-320 readily retrievable. The objective of this calculation is to perform the structural analysis of the Pipe Supports designed for Slurry and Supernate transfer pipe lines in order to meet the requirements of applicable ASME codes. The pipe support design loads are obtained from the piping stress calculations W320-27-I-4 and W320-27-I-5. These loads are the total summation of the gravity, pressure, thermal and seismic loads. Since standard typical designs are used for each type of pipe support such as Y-Stop, Guide and Anchors, each type of support is evaluated for the maximum loads to which this type of supports are subjected. These loads are obtained from the AutoPipe analysis and used to check the structural adequacy of these supports.
Comparison of different global information sources used in surface radiative flux calculation
), the Laboratoire de MeÂ´teÂ´orologie Dynamique, NOAA/NASA Pathfinder Advanced Very High Resolution Radiometer project Spectroradiometer product, the NASA Global Energy and Water Cycle Experiment Surface Radiation Budget project surface albedos in the near-infrared remain poorly constrained (highly uncertain), they do not cause too
Rasor, Robert Winston
1978-01-01T23:59:59.000Z
. IST 0F FIGURBS Figure Ideal Fracture Propagation Increase in l&roductivity From Fracturing Concentra l. !on Protile From Analytical l'odels A;"ier BabcockA Concentration Profi1e From Simulation Node'1 5 Bed Contigurat'ion for Analytical Solution... is described oy 0'?r! y's equation and is a funct ioi) of producing inLerval height. Therefor(', 1 low through a propped fracture is also a function of' !)ropi)&&nt !&ank he) qht. . Prc)dieting the + ina! oeometry of the proppant bank is easer tiai...
Quality Control Inspector: Different Programs, Different Responsibilit...
Broader source: Energy.gov (indexed) [DOE]
document explains the role of the Quality Control Inspector (QCI) in regards to the Home Energy Professional Certification Exam. Quality Control Inspector: Different Programs,...
Supplemental Reactor Physics Calculations and Analysis of ELF Mk 1A Fuel
Michael A. Pope
2014-10-01T23:59:59.000Z
These calculations supplement previous the reactor physics work evaluating the Enhanced Low Enriched Uranium (LEU) Fuel (ELF) Mk 1A element. This includes various additional comparisons between the current Highly Enriched Uranium (HEU) and LEU along with further characterization of the performance of the ELF fuel. The excess reactivity to be held down at BOC for ELF Mk 1A fuel is estimated to be approximately $2.75 greater than with HEU for a typical cycle. This is a combined effect of the absence of burnable poison in the ELF fuel and the reduced neck shim worth in LEU fuel compared to HEU. Burnable poison rods were conceptualized for use in the small B positions containing Gd2O3 absorber. These were shown to provide $2.37 of negative reactivity at BOC and to burn out in less than half of a cycle. The worth of OSCCs is approximately the same between HEU and ELF Mk 1A (LEU) fuels in the representative loading evaluated. This was evaluated by rotating all banks simultaneously. The safety rod worth is relatively unchanged between HEU and ELF Mk 1A (LEU) fuels in the representative loading evaluated. However, this should be reevaluated with different loadings. Neutron flux, both total and fast (>1 MeV), is either the same or reduced upon changing from HEU to ELF Mk 1A (LEU) fuels in the representative loading evaluated. This is consistent with the well-established trend of lower neutron fluxes for a given power in LEU than HEU.The IPT loop void reactivity is approximately the same or less positive with ELF Mk 1A (LEU) fuel than HEU in the representative loading evaluated.
Use of computers for multicomponent distillation calculations
Sullivan, Samuel Lane
1959-01-01T23:59:59.000Z
The corrected values for the b 's are best cal- i culated by multiplying (b. /d ) by (d. ) The compositions for each component in the vapor and liquid streams leaving plate j are calculated by use of the following equations. ('i/ i)ca ( i)co y. ji c Z (v... . . /b. ) (b. ) ji i ca i co i=1 , f a j x N+1 C (47-b) A temperature profile may be calculated by making either bubble or dew point calculations based on the compositions obtained by use of Equations (46) and (47). The specified distillate rate must...
Assessment of seismic margin calculation methods
Kennedy, R.P.; Murray, R.C.; Ravindra, M.K.; Reed, J.W.; Stevenson, J.D.
1989-03-01T23:59:59.000Z
Seismic margin review of nuclear power plants requires that the High Confidence of Low Probability of Failure (HCLPF) capacity be calculated for certain components. The candidate methods for calculating the HCLPF capacity as recommended by the Expert Panel on Quantification of Seismic Margins are the Conservative Deterministic Failure Margin (CDFM) method and the Fragility Analysis (FA) method. The present study evaluated these two methods using some representative components in order to provide further guidance in conducting seismic margin reviews. It is concluded that either of the two methods could be used for calculating HCLPF capacities. 21 refs., 9 figs., 6 tabs.
Calculated structures and fluoride affinities for fluorides
O'Keeffe, M.
1986-07-23T23:59:59.000Z
It is shown that SCF-MO calculations provide good estimates of the energies of the processes MF/sub n/ ..-->.. M/sup n+/ + nF/sup -/ where M/sup n+/ is an ion of a first- or second-row element in a closed-shell or s/sup 2/ configuration. The fluoride ion affinities are then calculated for a number of molecules and ions. Where comparison with experiment is possible, the agreement is generally good when allowance is made for experimental uncertainties. In favorable cases, accurate heats of formation may be calculated from fluoride affinities.
Calculation of external dose from distributed source
Kocher, D.C.
1986-01-01T23:59:59.000Z
This paper discusses a relatively simple calculational method, called the point kernel method (Fo68), for estimating external dose from distributed sources that emit photon or electron radiations. The principles of the point kernel method are emphasized, rather than the presentation of extensive sets of calculations or tables of numerical results. A few calculations are presented for simple source geometries as illustrations of the method, and references and descriptions are provided for other caluclations in the literature. This paper also describes exposure situations for which the point kernel method is not appropriate and other, more complex, methods must be used, but these methods are not discussed in any detail.
Tu, Kevin
, latent and carbon dioxide from eddy covariances presented by Kevin Tu, St. Louis (10/97). The properties
Calculations of crystal-melt interfacial free energies by nonequilibrium work measurements
Song, Xueyu
Calculations of crystal-melt interfacial free energies by nonequilibrium work measurements Yan Mu perturbation method to compute the interfacial free energies by nonequilibrium work measurements with cleaving potential procedure. Using this method, we calculated the interfacial free energies of different crystal
A Critical Assessment of Computer Tools for Calculating Composite Wind Turbine Blade Properties
Yu, Wenbin
A Critical Assessment of Computer Tools for Calculating Composite Wind Turbine Blade Properties Hui assess several computer tools for calculating the inertial and structural properties of wind turbine, and a realistic composite wind turbine blade are used to evaluate the performance of different tools
INDIRECT COST CALCULATION [IN REVERSE] YOU WANT TO CALCULATE THE DIRECT COSTS
Finley Jr., Russell L.
INDIRECT COST CALCULATION [IN REVERSE] YOU WANT TO CALCULATE THE DIRECT COSTS YOU KNOW WHAT THE TUITION, STIPEND AND EQUIPMENT COSTS ARE YOU KNOW WHAT THE TOTAL COST IS CALCULATION IS USING THE 2010 FED F&A RATE FOR WSU OF 52% (.52) [ DIRECT COST TUITION STIPEND EQUIPMENT] (.52 ) + DIRECT
Medical physics calculations with MCNP: a primer
Lazarine, Alexis D
2006-10-30T23:59:59.000Z
of Medical Internal Radiation Dose (MIRD) specific absorbed fraction (SAF) values using the ORNL MIRD phantom, x-ray phototherapy effectiveness, prostate brachytherapy lifetime dose calculations, and a radiograph of the head using the Zubal head phantom. Also...
Essential Value, Pmax, and Omax Automated Calculator
Kaplan, Brent A.; Reed, Derek D.
2014-08-21T23:59:59.000Z
Behavioral economic measures of demand are often calculated in sophisticated spreadsheet programs. Unfortunately, no closed form models for exact pmax (point of unit elasticity) and omax (response output at pmax) can be ...
Medical physics calculations with MCNP: a primer
Lazarine, Alexis D
2006-10-30T23:59:59.000Z
of Medical Internal Radiation Dose (MIRD) specific absorbed fraction (SAF) values using the ORNL MIRD phantom, x-ray phototherapy effectiveness, prostate brachytherapy lifetime dose calculations, and a radiograph of the head using the Zubal head phantom. Also...
Historical river flow rates for dose calculations
Carlton, W.H.
1991-06-10T23:59:59.000Z
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.
Available Energy Calculations for Process Engineers
Parker, A. L.
1982-01-01T23:59:59.000Z
Brief reviews of available energy and of the application of available energy analysis to chemical processes are given. Two alternative methods for performing available energy calculations are discussed and contrasted. The first method relies...
Calculator programs for pipe stress engineering
Morgan, K.S.
1985-01-01T23:59:59.000Z
This book contains a collection of programs for solving a wide variety of stress problems using both the TI-59 and HP-41CV calculators. Each program is prefaced with a description of the problem to be solved, nomenclature, code restrictions and program limitations. Solutions are explained analytically and then followed by the complete program listing, documentation and checklists. Topics include calculations for pipewall thickness, pressure vessel analysis, reinforcement pads, allowable span, vibration, stress, and two-anchor piping systems.
Calculator program speeds rod pump design
Engineer, R.; Davis, C.L.
1984-02-01T23:59:59.000Z
Matching sucker rod pump characteristics to a specific application is greatly simplified with this program, intended for use with an HP-41CV hand-held computer. The user inputs application data and the program calculates all necessary design criteria, including Mill's acceleration factor, peak and minimum polish rod loads and horsepower required. Sample calculations are provided, together with a thorough discussion of special design considerations involved in huff-and-puff applications.
Calculation of rotordynamic forces on labyrinth seals
Hensel, Steve John
1986-01-01T23:59:59.000Z
CALCULATION OF ROTORDYNAMIC FORCES ON LABYRINTH SEALS A Thesis STEVE JOHN HENSEL Submitted to the Graduate College of Texas AkM University in partial fulfillment of the requirement for the degree of MASTER OF SCIENCE December 1986 Major... Subject: Mechanical Engineering CALCULATION OF ROTORDYNAMIC FORCES ON LABYRINTH SEALS A Thesis by STEVE JOHN HENSEL Approved as to style snd content by: David Rhode (Chairman of Committee) Erian Baskharone Leel and Garison (Member) +, gg, W. D...
Barlich, G.L.; Nasseri, S.S.
1990-01-01T23:59:59.000Z
Good decision-making in materials accounting requires a valid calculation of control limits and detection sensitivity for facilities handling special nuclear materials (SNM). A difficult aspect of this calculation is determining the appropriate variance and covariance values for the terms in the materials balance (MB) equation. Computer software such as MAVARIC (Materials Accounting VARIance Calculator) and PROFF (PROcessing and Fuel Facilities calculator) can efficiently select and combine variance terms. These programs determine the variance and covariance of an MB equation by first obtaining relations for the variance and covariance of each term in the MB equation through propagating instrument errors and then substituting the measured quantities and their uncertainties into these relations. MAVARIC is a custom spreadsheet used with the second release of LOTUS 1-2-3.** PROFF is a stand-alone menu-driven program requiring no commercial software. Programs such as MAVARIC and PROFF facilitate the complex calculations required to determine the detection sensitivity of an SNM facility. These programs can also be used to analyze materials accounting systems.
Calculation of conventional and prompt lepton fluxes at very high energy
Fedynitch, Anatoli; Gaisser, Thomas K; Riehn, Felix; Stanev, Todor
2015-01-01T23:59:59.000Z
An efficient method for calculating inclusive conventional and prompt atmospheric leptons fluxes is presented. The coupled cascade equations are solved numerically by formulating them as matrix equation. The presented approach is very flexible and allows the use of different hadronic interaction models, realistic parametrizations of the primary cosmic-ray flux and the Earth's atmosphere, and a detailed treatment of particle interactions and decays. The power of the developed method is illustrated by calculating lepton flux predictions for a number of different scenarios.
End-to-end calculation of the radiation characteristics of VVER-1000 spent fuel assemblies
Linge, I. I.; Mitenkova, E. F., E-mail: mit@ibrae.ac.ru; Novikov, N. V. [Russian Academy of Sciences, Nuclear Safety Institute (Russian Federation)
2012-12-15T23:59:59.000Z
The results of end-to-end calculation of the radiation characteristics of VVER-1000 spent nuclear fuel are presented. Details of formation of neutron and gamma-radiation sources are analyzed. Distributed sources of different types of radiation are considered. A comparative analysis of calculated radiation characteristics is performed with the use of nuclear data from different ENDF/B and EAF files and ANSI/ANS and ICRP standards.
Pastore, S. [University of South Carolina; Wiringa, Robert B. [ANL; Pieper, Steven C. [ANL; Schiavilla, Rocco [Old Dominion U., JLAB
2014-08-01T23:59:59.000Z
We report quantum Monte Carlo calculations of electromagnetic transitions in $^8$Be. The realistic Argonne $v_{18}$ two-nucleon and Illinois-7 three-nucleon potentials are used to generate the ground state and nine excited states, with energies that are in excellent agreement with experiment. A dozen $M1$ and eight $E2$ transition matrix elements between these states are then evaluated. The $E2$ matrix elements are computed only in impulse approximation, with those transitions from broad resonant states requiring special treatment. The $M1$ matrix elements include two-body meson-exchange currents derived from chiral effective field theory, which typically contribute 20--30\\% of the total expectation value. Many of the transitions are between isospin-mixed states; the calculations are performed for isospin-pure states and then combined with the empirical mixing coefficients to compare to experiment. In general, we find that transitions between states that have the same dominant spatial symmetry are in decent agreement with experiment, but those transitions between different spatial symmetries are often significantly underpredicted.
The status of nuclear data for transmutation calculations
Wilson, W.B.; England, T.R.; MacFarlane, R.E.; Muir, D.W.; Young, P.G.
1995-12-01T23:59:59.000Z
At this point, the accurate description of transmutation products in a radiation environment is more a nuclear data problem than a code development effort. We have used versions of the CINDER code for over three decades to describe the transmutation of nuclear reactor fuels in radiation environments. The need for the accurate description of reactor neutron-absorption, decay-power, and decay-spectra properties have driven many AEC, ERDA, and DOE supported nuclear data development efforts in this period. The level of cross-section, decay, and fission-yield data has evolved from rudimentary to a comprehensive ENDF/B-VI library permitting great precision in reactor calculations. The precision of the data supporting reactor simulations provides a sturdy foundation for the data base required for the wide range of transmutation problems currently studied. However, such reactor problems are typically limited to neutron energies below 10 MeV or so; reaction and decay data are required for actinides of, say, 90 {le} Z {le} 96 neutron-rich fission products of 22 {le} Z {le} 72. The expansion into reactor structural materials and fusion systems extends these ranges in energy and Z somewhat. The library of nuclear data, constantly growing in breadth and quality with international cooperation, is now described in the following table.
Quantum Monte Carlo Calculations of Light Nuclei Using Chiral Potentials
J. E. Lynn; J. Carlson; E. Epelbaum; S. Gandolfi; A. Gezerlis; A. Schwenk
2014-11-09T23:59:59.000Z
We present the first Green's function Monte Carlo calculations of light nuclei with nuclear interactions derived from chiral effective field theory up to next-to-next-to-leading order. Up to this order, the interactions can be constructed in a local form and are therefore amenable to quantum Monte Carlo calculations. We demonstrate a systematic improvement with each order for the binding energies of $A=3$ and $A=4$ systems. We also carry out the first few-body tests to study perturbative expansions of chiral potentials at different orders, finding that higher-order corrections are more perturbative for softer interactions. Our results confirm the necessity of a three-body force for correct reproduction of experimental binding energies and radii, and pave the way for studying few- and many-nucleon systems using quantum Monte Carlo methods with chiral interactions.
ASME PTC 47 -- Calculation of overall IGCC plant performance
Xiong, T.; Horazak, D.A.
1999-07-01T23:59:59.000Z
An integrated gasification combined cycle (IGCC) plant is a combined chemical and power system that converts coal or other unrefined fuel into clean gaseous fuel, electric power, and other byproducts. The conversion process requires interactions among the gasification, gas cleaning, air or oxygen production, power and steam generation systems. Overall performance testing of IGCC plants. however, is based only on the streams that cross the overall plant boundary. This paper describes the calculation procedures required to conduct a fair and accurate performance test of an IGCC plant, as proposed for ASME Performance Test Code 47. Discussions include identification of parameters to be measured, calculations needed to evaluate performance, and corrections to performance data for test conditions that differ from reference conditions.
MCNP photon transport benchmarking calculations performed at SRP. Revision 1
White, A.M.
1989-12-31T23:59:59.000Z
Monte Carlo methods have long been used at the Savannah River Laboratory (SRL) to perform criticality calculations for many different processes. To perform transport analyses (both neutron and photon) a two-dimensional infinite lattice integral transport code (GLASS) has been used. The neutron transport portion of the code has been benchmarked against other codes and experimental data. The photon transport portion of the code, which is used to calculate gamma redistribution in the event of a loss of moderator and/or coolant, had not been benchmarked against either. For this reason, the Monte Carlo code MCNP was used to benchmark the photon transport portion of the GLASS code. Preceding this, a brief description of the geometry of the Savannah River Plant`s (SRP) reactor cores and how they were modeled using MCNP will be given.
Numerical calculations of ultrasonic fields I: transducer near fields
Johnson, J.A.
1982-03-01T23:59:59.000Z
A computer code for the calculation of linear acoustic wave propagation in homogeneous fluid and solid materials has been derived from the thermal-hydraulics code STEALTH. The code uses finite-difference techniques in a two-dimensional mesh made up of arbitrarily shaped quadrilaterals. Problems with two-dimensional plane strain or two-dimensional axial symmetries can be solved. Free, fixed, or stressed boundaries can be used. Transducers can be modeled by time dependent boundary conditions or by moving pistons. This paper gives a brief description of the method and shows the results of the calculation of the near fields of circular flat and focused transducers. These results agree with analytic theory along the axis of symmetry and with other codes that use a Huygens reconstruction technique off-axis.
Numerical calculations of ultrasonic fields I: transducer near fields
Johnson, J.A.
1982-04-01T23:59:59.000Z
A computer code for the calculation of linear acoustic wave propagation in homogeneous fluid and solid materials has been derived from the thermal-hydraulics code STEALTH. The code uses finite-difference techniques in a two dimensional mesh made up of arbitrarily shaped quadrilaterals. Problems with two dimensional plane strain or two dimensional axial symmetries can be solved. Free, fixed or stressed boundaries can be used. Transducers can be modeled by time dependent boundary conditions or by moving pistons. A brief description of the method is given and the results of the calculation of the near fields of circular flat and focused transducers are shown. These results agree with analytic theory along the axis of symmetry and with other codes that use a Huygens' reconstruction technique off axis.
Solid-State Calculation of Crystalline Color Superconductivity
Cao, Gaoqing; Zhuang, Pengfei
2015-01-01T23:59:59.000Z
It is generally believed that the inhomogeneous Larkin-Ovchinnikov-Fulde-Ferrell (LOFF) phase appears in a color superconductor when the pairing between different quark flavors is under the circumstances of mismatched Fermi surfaces. However, the real crystal structure of the LOFF phase is still unclear because an exact treatment of 3D crystal structures is rather difficult. In this work we calculate the ground-state energy of the body-centered cubic (BCC) structure for two-flavor pairing by diagonalizing the Hamiltonian matrix in the Bloch space, in analogy to the \\emph{ab initio} calculations in solid-state physics. We develop a computational scheme to overcome the difficulties in diagonalizing huge matrices. Our results show that the BCC structure is energetically more favorable than the 1D modulation in a narrow window around the conventional LOFF-normal phase transition point, which indicates the significance of the higher-order terms in the Ginzburg-Landau approach.
Benchmarking kinetic calculations of resistive wall mode stability
Berkery, J. W.; Sabbagh, S. A. [Department of Applied Physics and Applied Mathematics, Columbia University, New York, New York 10027 (United States)] [Department of Applied Physics and Applied Mathematics, Columbia University, New York, New York 10027 (United States); Liu, Y. Q. [Euratom/CCFE Fusion Association, Culham Science Centre, Abingdon OX14 3DB (United Kingdom)] [Euratom/CCFE Fusion Association, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); Wang, Z. R.; Logan, N. C.; Park, J.-K.; Manickam, J. [Princeton Plasma Physics Laboratory, Princeton University, Princeton, New Jersey 08543 (United States)] [Princeton Plasma Physics Laboratory, Princeton University, Princeton, New Jersey 08543 (United States); Betti, R. [Laboratory for Laser Energetics, University of Rochester, Rochester, New York 14623 (United States)] [Laboratory for Laser Energetics, University of Rochester, Rochester, New York 14623 (United States)
2014-05-15T23:59:59.000Z
Validating the calculations of kinetic resistive wall mode (RWM) stability is important for confidently predicting RWM stable operating regions in ITER and other high performance tokamaks for disruption avoidance. Benchmarking the calculations of the Magnetohydrodynamic Resistive Spectrum—Kinetic (MARS-K) [Y. Liu et al., Phys. Plasmas 15, 112503 (2008)], Modification to Ideal Stability by Kinetic effects (MISK) [B. Hu et al., Phys. Plasmas 12, 057301 (2005)], and Perturbed Equilibrium Nonambipolar Transport (PENT) [N. Logan et al., Phys. Plasmas 20, 122507 (2013)] codes for two Solov'ev analytical equilibria and a projected ITER equilibrium has demonstrated good agreement between the codes. The important particle frequencies, the frequency resonance energy integral in which they are used, the marginally stable eigenfunctions, perturbed Lagrangians, and fluid growth rates are all generally consistent between the codes. The most important kinetic effect at low rotation is the resonance between the mode rotation and the trapped thermal particle's precession drift, and MARS-K, MISK, and PENT show good agreement in this term. The different ways the rational surface contribution was treated historically in the codes is identified as a source of disagreement in the bounce and transit resonance terms at higher plasma rotation. Calculations from all of the codes support the present understanding that RWM stability can be increased by kinetic effects at low rotation through precession drift resonance and at high rotation by bounce and transit resonances, while intermediate rotation can remain susceptible to instability. The applicability of benchmarked kinetic stability calculations to experimental results is demonstrated by the prediction of MISK calculations of near marginal growth rates for experimental marginal stability points from the National Spherical Torus Experiment (NSTX) [M. Ono et al., Nucl. Fusion 40, 557 (2000)].
On the Sensitivity of ?/? Prediction to Dose Calculation Methodology in Prostate Brachytherapy
Afsharpour, Hossein [Centre de Recherche sur le Cancer, Université Laval and Département de Radio-Oncologie, Centre Hospitalier Universitaire de Québec, Québec, QC (Canada); Centre Intégré de Cancérologie de la Montérégie, Hôpital Charles-LeMoyne, Greenfield Park, QC (Canada); Walsh, Sean [Department of Radiation Oncology Maastricht Radiation Oncology (MAASTRO), GROW, University Hospital Maastricht, Maastricht (Netherlands); Gray Institute for Radiation Oncology and Biology, The University of Oxford, The United Kingdom (United Kingdom); Collins Fekete, Charles-Antoine; Vigneault, Eric [Centre de Recherche sur le Cancer, Université Laval and Département de Radio-Oncologie, Centre Hospitalier Universitaire de Québec, Québec, QC (Canada); Verhaegen, Frank [Department of Radiation Oncology Maastricht Radiation Oncology (MAASTRO), GROW, University Hospital Maastricht, Maastricht (Netherlands); Medical Physics Unit, Department of Oncology, McGill University, Montréal, Québec (Canada); Beaulieu, Luc, E-mail: Luc.Beaulieu@phy.ulaval.ca [Centre de Recherche sur le Cancer, Université Laval and Département de Radio-Oncologie, Centre Hospitalier Universitaire de Québec, Québec, QC (Canada)
2014-02-01T23:59:59.000Z
Purpose: To study the relationship between the accuracy of the dose calculation in brachytherapy and the estimations of the radiosensitivity parameter, ?/?, for prostate cancer. Methods and Materials: In this study, Monte Carlo methods and more specifically the code ALGEBRA was used to produce accurate dose calculations in the case of prostate brachytherapy. Equivalent uniform biologically effective dose was calculated for these dose distributions and was used in an iso-effectiveness relationship with external beam radiation therapy. Results: By considering different levels of detail in the calculations, the estimation for the ?/? parameter varied from 1.9 to 6.3 Gy, compared with a value of 3.0 Gy suggested by the American Association of Physicists in Medicine Task Group 137. Conclusions: Large variations of the ?/? show the sensitivity of this parameter to dose calculation modality. The use of accurate dose calculation engines is critical for better evaluating the biological outcomes of treatments.
Brachytherapy structural shielding calculations using Monte Carlo generated, monoenergetic data
Zourari, K.; Peppa, V.; Papagiannis, P., E-mail: ppapagi@phys.uoa.gr [Medical Physics Laboratory, Medical School, University of Athens, 75 Mikras Asias, 11527 Athens (Greece); Ballester, Facundo [Department of Atomic, Molecular and Nuclear Physics, University of Valencia, Burjassot 46100 (Spain)] [Department of Atomic, Molecular and Nuclear Physics, University of Valencia, Burjassot 46100 (Spain); Siebert, Frank-André [Clinic of Radiotherapy, University Hospital of Schleswig-Holstein, Campus Kiel 24105 (Germany)] [Clinic of Radiotherapy, University Hospital of Schleswig-Holstein, Campus Kiel 24105 (Germany)
2014-04-15T23:59:59.000Z
Purpose: To provide a method for calculating the transmission of any broad photon beam with a known energy spectrum in the range of 20–1090 keV, through concrete and lead, based on the superposition of corresponding monoenergetic data obtained from Monte Carlo simulation. Methods: MCNP5 was used to calculate broad photon beam transmission data through varying thickness of lead and concrete, for monoenergetic point sources of energy in the range pertinent to brachytherapy (20–1090 keV, in 10 keV intervals). The three parameter empirical model introduced byArcher et al. [“Diagnostic x-ray shielding design based on an empirical model of photon attenuation,” Health Phys. 44, 507–517 (1983)] was used to describe the transmission curve for each of the 216 energy-material combinations. These three parameters, and hence the transmission curve, for any polyenergetic spectrum can then be obtained by superposition along the lines of Kharrati et al. [“Monte Carlo simulation of x-ray buildup factors of lead and its applications in shielding of diagnostic x-ray facilities,” Med. Phys. 34, 1398–1404 (2007)]. A simple program, incorporating a graphical user interface, was developed to facilitate the superposition of monoenergetic data, the graphical and tabular display of broad photon beam transmission curves, and the calculation of material thickness required for a given transmission from these curves. Results: Polyenergetic broad photon beam transmission curves of this work, calculated from the superposition of monoenergetic data, are compared to corresponding results in the literature. A good agreement is observed with results in the literature obtained from Monte Carlo simulations for the photon spectra emitted from bare point sources of various radionuclides. Differences are observed with corresponding results in the literature for x-ray spectra at various tube potentials, mainly due to the different broad beam conditions or x-ray spectra assumed. Conclusions: The data of this work allow for the accurate calculation of structural shielding thickness, taking into account the spectral variation with shield thickness, and broad beam conditions, in a realistic geometry. The simplicity of calculations also obviates the need for the use of crude transmission data estimates such as the half and tenth value layer indices. Although this study was primarily designed for brachytherapy, results might also be useful for radiology and nuclear medicine facility design, provided broad beam conditions apply.
Improved Calculation of Thermal Fission Energy
Ma, X B; Wang, L Z; Chen, Y X; Cao, J
2013-01-01T23:59:59.000Z
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.
Giant magnetoresistance calculated from first principles
Butler, W.H. [Oak Ridge National Lab., TN (United States); MacLaren, J.M. [Tulane Univ., New Orleans, LA (United States). Dept. of Physics; Zhang, X.G. [Univ. of Kentucky, Lexington, KY (United States). Center for Computational Sciences
1994-09-01T23:59:59.000Z
The Layer Korringa Kohn Rostoker-Coherent Potential Approximation technique was used to calculate the low temperature Giant Magnetoresistance from first principles for Co{vert_bar}Cu and permalloy{vert_bar}Cu superlattices. Our calculations predict large giant magnetoresistance ratios for Co{vert_bar}Cu and extremely large ratios for permalloy{vert_bar}Cu for current perpendicular to the layers. Mechanisms such as spin-orbit coupling which mix spin channels are expected to greatly reduce the GMR effect for permalloy{vert_bar}Cu.
Calculation method for safe ?* in the LHC
Bruce, R; Herr, W; Wollmann, D
2011-01-01T23:59:59.000Z
One way of increasing the peak luminosity in the LHC is to decrease the beam size at the interaction points by squeezing to smaller values of ?*. The LHC is now in a regime where safety and stability determines the limit on ?*, as opposed to traditional optics limits. In this paper, we derive a calculation model to determine the safe ?*-values based on collimator settings and operational stability of the LHC. This model was used to calculate the settings for the LHC run in 2011. It was found that ?* could be decreased from 3.5 m to 1.5 m, which has now successfully been put into operation.
Nonperturbative calculations in light-front QED
Chabysheva, Sophia S. [Department of Physics, University of Minnesota-Duluth, Duluth, Minnesota 55812 (United States)
2010-12-22T23:59:59.000Z
The methods of light-front quantization and Pauli-Villars regularization are applied to a nonperturbative calculation of the dressed-electron state in quantum electrodynamics. This is intended as a test of the methods in a gauge theory, as a precursor to possible methods for the nonperturbative solution of quantum chromodynamics. The electron state is truncated to include at most two photons and no positrons in the Fock basis, and the wave functions of the dressed state are used to compute the electrons's anomalous magnetic moment. A choice of regularization that preserves the chiral symmetry of the massless limit is critical for the success of the calculation.
Fully Automated Calculations in the complex MSSM
T. Hahn; S. Heinemeyer; F. von der Pahlen; H. Rzehak; C. Schappacher
2014-07-01T23:59:59.000Z
We review recent progress towards automated higher-order calculations in the MSSM with complex parameters (cMSSM). The consistent renormalization of all relevant sectors of the cMSSM and the inclusion into the FeynArts/FormCalc framework has recently been completed. Some example calculations applying this framework are briefly discussed. These include two-loop corrections to cMSSM Higgs boson masses as well as partial decay widths of electroweak supersymmetric particles decaying into a Higgs boson and another supersymmetric particle.
Heat Exchanger Support Bracket Design Calculations
Rucinski, Russ; /Fermilab
1995-01-12T23:59:59.000Z
This engineering note documents the design of the heat exchanger support brackets. The heat exchanger is roughly 40 feet long, 22 inches in diameter and weighs 6750 pounds. It will be mounted on two identical support brackets that are anchored to a concrete wall. The design calculations were done for one bracket supporting the full weight of the heat exchanger, rounded up to 6800 pounds. The design follows the American Institute of Steel Construction (AISC) Manual of steel construction, Eighth edition. All calculated stresses and loads on welds were below allowables.
A PROCEDURE FOR CALCULATING INTERIOR DAYLIGHT ILLUMINATION WITH A PROGRAMMABLE HAND CALCULATOR
Bryan, H.J.
2010-01-01T23:59:59.000Z
FOR CALCULATING INTERIOR DAYLIGHT ILLUMINATION WITH ACommittee E-3.2, "Daylight: International RecommendationsCalcula- tion of Natural Daylight," CIE PUBLICATION No. 16,
Kurova, N. V., E-mail: kurova_natasha@mail.ru; Burdov, V. A. [Lobachevskii Nizhni Novgorod State University (Russian Federation)
2013-12-15T23:59:59.000Z
The results of ab initio calculations of the electronic structure of Si nanocrystals doped with shallow donors (Li, P) are reported. It is shown that phosphorus introduces much more significant distortions into the electronic structure of the nanocrystal than lithium, which is due to the stronger central cell potential of the phosphorus ion. It is found that the Li-induced splitting of the ground state in the conduction band of the nanocrystal into the singlet, doublet, and triplet retains its inverse structure typical for bulk silicon.
Novel Approach for Calculation and Analysis of Eigenvalues and Eigenvectors in Microgrids: Preprint
Li, Y.; Gao, W.; Muljadi, E.; Jiang, J.
2014-02-01T23:59:59.000Z
This paper proposes a novel approach based on matrix perturbation theory to calculate and analyze eigenvalues and eigenvectors in a microgrid system. Rigorous theoretical analysis to solve eigenvalues and the corresponding eigenvectors for a system under various perturbations caused by fluctuations of irradiance, wind speed, or loads is presented. A computational flowchart is proposed for the unified solution of eigenvalues and eigenvectors in microgrids, and the effectiveness of the matrix perturbation-based approach in microgrids is verified by numerical examples on a typical low-voltage microgrid network.
Latkowski, J.F. [Lawrence Livermore National Lab., CA (United States); Sanz, J. [Universidad Politecnica de Madrid (Spain); Vujic, J.L. [Univ. of California, Berkeley, CA (United States)
1996-12-31T23:59:59.000Z
Sisolak et al. defined two methods for the approximation of pulsed irradiation: the steady-state (SS) and the equivalent steady-state (ESS) methods. Both methods have been shown to greatly simplify the process of calculating radionuclide inventories. However, they are not accurate when applied to magnetic fusion energy (MFF) and inertial fusion energy (IFE) experimental facilities. In the work reported here, an attempt has been made to evaluate the accuracy of the SS and ESS methods as they might be applied to typical MFE and IFE power plants. 18 refs., 6 figs.
High School or PSEO: Important Differences to Consider
Amin, S. Massoud
High School or PSEO: Important Differences to Consider High School College High school set priorities Most classes are arranged for you The school year is typically 36 weeks long You may Teachers often arrange test dates to avoid conflict with school events Grades are given for most assigned
Envelope calculations for a low temperature neutron star
McCoy, Robert Paul
1976-01-01T23:59:59.000Z
with distance inward from the surface R for all three star models S, I and II at effective temperature Te = 10 K 34 Density-pressure dependence for the Model S star at different values of Te 35 Envelope calculation traces in the opacity-density plane... )] (20) Similarly a relation between p and T can be found 64v GN~ uH() a+1 1 a+1 ~a+ 3 r L k 4-b+aJ 0 (21) Inserting this back into the energy transport equation (13) gives the radial dependence of the temperature (22) (23) where R is the surface...
Calculation of material properties and ray tracing in transformation media
Schurig, D; Smith, D R
2006-01-01T23:59:59.000Z
Complex and interesting electromagnetic behavior can be found in spaces with non-flat topology. When considering the properties of an electromagnetic medium under an arbitrary coordinate transformation an alternative interpretation presents itself. The transformed material property tensors may be interpreted as a different set of material properties in a flat, Cartesian space. We describe the calculation of these material properties for coordinate transformations that describe spaces with spherical or cylindrical holes in them. The resulting material properties can then implement invisibility cloaks in flat space. We also describe a method for performing geometric ray tracing in these materials which are both inhomogeneous and anisotropic in their electric permittivity and magnetic permeability.
Oberseminar -ICP Temperature Calculation for Tribological
Harting, Jens
and passing to third parties. 0 #12;Overview Where to calculate the heat: diesel injection pump First focus: journal bearings DS/ETI2 Vortrag 24.01.05.tex 24.01.05 c Robert Bosch GmbH reserves all rights even;Approach Some assessments: Heat diffuses 30µm in diesel in the time of one rotation of the shaft
New correlation calculates reliable paraffin solubilities
Yaws, C.L.; Pan, X. (Lamar Univ., Beaumont, TX (US))
1991-04-08T23:59:59.000Z
A new correlation based on boiling point has been developed which accurately calculates paraffin solubilities in water. The correlation provides reliable solubility values down to very low concentrations (parts per million and less), for which the API correlation is not accurate. It can be used for initial engineering studies, including those involving health, safety, and environmental considerations.
Spin Contamination in Inorganic Chemistry Calculations
Schlegel, H. Bernhard
R EVISED PAG E PR O O FS ia617 Spin Contamination in Inorganic Chemistry Calculations Jason L . In such cases, 0 is said to be spin contaminated owing to incorporation of higher spin state character of IronSulfur ia618 Clusters). It is important to note that while spin-contaminated and broken
Calculation of a coaxial microwave torch
Gritsinin, S. I.; Kossyi, I. A. [Russian Academy of Sciences, Prokhorov Institute of General Physics (Russian Federation); Kulumbaev, E. B.; Lelevkin, V. M. [Kyrgyz-Russian Slavic University (Kyrgyzstan)
2006-10-15T23:59:59.000Z
Parameters of an equilibrium microwave discharge in an atmospheric-pressure argon flow in a coaxial waveguide with a truncated inner electrode are calculated numerically by using a self-consistent two-dimensional MHD model. The results obtained agree satisfactorily with the experimental data.
Damien Allain Ingnieur recherche, dveloppement, calcul scientifique
, 5 articles publiÃ©s. Â· Administration du parc de machines de calculs Linux. 01/2003Â03/2003 IngÃ©nieur donnÃ©es, la rÃ©paration de code source en C/C++, de tÃ©lÃ©chargement de patch et de conversion d'image pour
CALCULATING THE CARBON FOOTPRINT SUPPLY CHAIN FOR
Su, Xiao
CALCULATING THE CARBON FOOTPRINT SUPPLY CHAIN FOR THE SEMICONDUCTOR INDUSTRY By: Yasser Dessouky #12;Carbon Footprint Supply Chain Carbon Trust defines carbon footprint of a supply chain as follows: "The carbon footprint of a product is the carbon dioxide emitted across the supply chain for a single
2004 NET SYSTEM POWER CALCULATION COMMISSIONREPORT
CALIFORNIA ENERGY COMMISSION 2004 NET SYSTEM POWER CALCULATION COMMISSIONREPORT April 2005 CEC-300 on net system power [Senate Bill 1305, (Sher), Chapter 796, Statute of 1997]1 . Net system power in California. Net system power plays a role in California's retail disclosure program, which requires every
Consanguine Calculations Input File: blood.in
California at Berkeley, University of
1 of 20 Problem A+ Consanguine Calculations Input File: blood.in Every person's blood has 2 markers in a particular ABO blood type for that person. Combination ABO Blood Type AA A AB AB AO A BB B BO B OO O Likewise, every person has two alleles for the blood Rh factor, represented by the characters + and -. Someone who
Program performs vapor-liquid equilibrium calculations
Rice, V.L.
1982-06-28T23:59:59.000Z
A program designed for the Hewlett-Packard HP-41CV or 41C calculators solves basic vapor-liquid equilibrium problems, including figuring the dewpoint, bubblepoint, and equilibrium flash. The algorithm uses W.C. Edmister's method for predicting ideal-solution K values.
FIRST PRINCIPLES CALCULATIONS OF TOKAMAK ENERGY TRANSPORT
Hammett, Greg
energy losses have prevented the experimental demonstration of net fusion energy production fromFIRST PRINCIPLES CALCULATIONS OF TOKAMAK ENERGY TRANSPORT M. KOTSCHENREUTHER, W. DORLAND, Q.P. LIU Institute for Fusion Studies, University of Texas, Austin, Texas, United States of America G.W. HAMMETT, M
Beshr, Mohamed [University of Maryland, College Park; Aute, Vikrant [University of Maryland, College Park; Abdelaziz, Omar [ORNL; Fricke, Brian A [ORNL; Radermacher, Reinhard [University of Maryland, College Park
2014-01-01T23:59:59.000Z
Commercial refrigeration systems consumed 1.21 Quads of primary energy in 2010 and are known to be a major source for refrigerant charge leakage into the environment. Thus, it is important to study the environmental impact of commercial supermarket refrigeration systems and improve their design to minimize any adverse impacts. The system s Life Cycle Climate Performance (LCCP) was presented as a comprehensive metric with the aim of calculating the equivalent mass of carbon dioxide released into the atmosphere throughout its lifetime, from construction to operation and destruction. In this paper, an open source tool for the evaluation of the LCCP of different air-conditioning and refrigeration systems is presented and used to compare the environmental impact of a typical multiplex direct expansion (DX) supermarket refrigeration systems based on three different refrigerants as follows: two hydrofluorocarbon (HFC) refrigerants (R-404A, and R-407F), and a low global warming potential (GWP) refrigerant (N-40). The comparison is performed in 8 US cities representing different climates. The hourly energy consumption of the refrigeration system, required for the calculation of the indirect emissions, is calculated using a widely used building energy modeling tool (EnergyPlus). A sensitivity analysis is performed to determine the impact of system charge and power plant emission factor on the LCCP results. Finally, we performed an uncertainty analysis to determine the uncertainty in total emissions for both R-404A and N-40 operated systems. We found that using low GWP refrigerants causes a considerable drop in the impact of uncertainty in the inputs related to direct emissions on the uncertainty of the total emissions of the system.
Development of finite-difference equations for variance of neutron fluxes in reactor
Laletin, N. I., E-mail: nil@adis.vver.kiae.ri; Kovalishin, A. A., E-mail: kaa@adis.vver.kiae.ri [Russian Research Center Kurchatov Institute (Russian Federation)
2010-12-15T23:59:59.000Z
Different sources-methodical, constant, and technological-are discussed for uncertainties in calculation functionals. The basic principles of three methods used in calculations of uncertainties are briefly described.
Calculation of wake power losses in a two-level array: a simple case study
Barnard, J.C.
1985-12-01T23:59:59.000Z
One method of adding capacity is to install another array of turbines whose hub height is above the existing array. This report estimates the wake interference that could be expected in a two-level array. Interference is estimated for a typical situation that may be encountered by a wind farm developer. A modified Lissaman array model is used to make the wake interference calculations. The model calculations show that the wake interference between the two levels is small for the turbine characteristics and turbine layouts considered. (The windwise spacings are about 5.4 and 10.8D for the lower and upper levels of turbines, respectively.) Power losses are about 5% or less at rated speed. Thus, two-level arrays may be a viable way of increasing the generating capacity of existing wind farms.
Individual Differences in Human Reliability Analysis
Jeffrey C. Joe; Ronald L. Boring
2014-06-01T23:59:59.000Z
While human reliability analysis (HRA) methods include uncertainty in quantification, the nominal model of human error in HRA typically assumes that operator performance does not vary significantly when they are given the same initiating event, indicators, procedures, and training, and that any differences in operator performance are simply aleatory (i.e., random). While this assumption generally holds true when performing routine actions, variability in operator response has been observed in multiple studies, especially in complex situations that go beyond training and procedures. As such, complexity can lead to differences in operator performance (e.g., operator understanding and decision-making). Furthermore, psychological research has shown that there are a number of known antecedents (i.e., attributable causes) that consistently contribute to observable and systematically measurable (i.e., not random) differences in behavior. This paper reviews examples of individual differences taken from operational experience and the psychological literature. The impact of these differences in human behavior and their implications for HRA are then discussed. We propose that individual differences should not be treated as aleatory, but rather as epistemic. Ultimately, by understanding the sources of individual differences, it is possible to remove some epistemic uncertainty from analyses.
CANISTER HANDLING FACILITY CRITICALITY SAFETY CALCULATIONS
C.E. Sanders
2005-04-07T23:59:59.000Z
This design calculation revises and updates the previous criticality evaluation for the canister handling, transfer and staging operations to be performed in the Canister Handling Facility (CHF) documented in BSC [Bechtel SAIC Company] 2004 [DIRS 167614]. The purpose of the calculation is to demonstrate that the handling operations of canisters performed in the CHF 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 ''Canister Handling Facility Description Document'' (BSC 2004 [DIRS 168992], Sections 3.1.1.3.4.13 and 3.2.3). Specific scope of work contained in this activity consists of updating the Category 1 and 2 event sequence evaluations as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2004 [DIRS 167268], Section 7). The CHF is limited in throughput capacity to handling sealed U.S. Department of Energy (DOE) spent nuclear fuel (SNF) and high-level radioactive waste (HLW) canisters, defense high-level radioactive waste (DHLW), naval canisters, multicanister overpacks (MCOs), vertical dual-purpose canisters (DPCs), and multipurpose canisters (MPCs) (if and when they become available) (BSC 2004 [DIRS 168992], p. 1-1). It should be noted that the design and safety analyses of the naval canisters are the responsibility of the U.S. Department of the Navy (Naval Nuclear Propulsion Program) and will not be included in this document. In addition, this calculation is valid for the current design of the CHF 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. This calculation is subject to the ''Quality Assurance Requirements and Description'' (DOE 2004 [DIRS 171539]) because the CHF is included in the Q-List (BSC 2005 [DIRS 171190], p. A-3) as an item important to safety. This calculation is prepared in accordance with AP-3.12Q, ''Design Calculations and Analyses'' [DIRS 168413].
Free energy differences : Representations, estimators, and sampling strategies
Acharya, Arjun R
In this thesis we examine methodologies for determining free energy differences (FEDs) of phases via Monte Carlo simulation. We identify and address three generic issues that arise in FED calculations; the choice of ...
Escher, Christine
-called "biodegradable" plastic products will safely break down in a typical commercial composting facility. www
Validation of Dose Calculation Codes for Clearance
Menon, S.; Wirendal, B.; Bjerler, J.; Studsvik; Teunckens, L.
2003-02-27T23:59:59.000Z
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.
HP-41 Calculates Dykstra-Parsons permeability
Bixler, B.
1983-07-01T23:59:59.000Z
A new program for the HP-41 programmable calculator has been written which will calculate the often used Dykstra-Parsons permeability variation factor, V. No longer must numerous individual permeability values be plotted on log probability paper as a first step in determining V. Input is simply these same permeability values selected at equal spacing along the interval in question. For most core analysis this spacing will be 1 ft. This program is labeled ''KVAR'' (for permeability variation) and is listed here, along with its bar code for those with optical wands. It requires only nine registers for program storage (since it uses HP built-in statistical functions) and eight registers for data storage. Also, it can be stored on one track of the standard two-track magnetic card. Data entry is terminated by entering ''O''. Lastly, it will run with or without a printer.
Analytic calculation of properties of holographic superconductors
George Siopsis; Jason Therrien
2010-03-22T23:59:59.000Z
We calculate analytically properties of holographic superconductors in the probe limit. We analyze the range $1/2 3/2$. We also obtain the frequency dependence of the conductivity by solving analytically the wave equation of electromagnetic perturbations. We show that the real part of the DC conductivity behaves as $e^{-\\Delta_g /T}$ and estimate the gap $\\Delta_g$ analytically. Our results are in good agreement with numerical results.
Free Energy Calculation in MD Simulation
Nielsen, Steven O.
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
Diffusion Simulation and Lifetime Calculation at RHIC
Abreu,N.P.; Fischer, W.; Luo, Y.; Robert-Demolaize, G.
2009-01-02T23:59:59.000Z
The beam lifetime is an important parameter for any storage ring. For protons in RHIC it is dominated by the non-linear nature of the head-on collisions that causes the particles to diffuse outside the stable area in phase space. In this report we show results from diffusion simulation and lifetime calculation for the 2006 and 2008 polarized proton runs in RHIC.
Structure and vibrations of different charge Ge impurity in ?-quartz
Kislov, A. N., E-mail: a.n.kislov@urfu.ru; Mikhailovich, A. P., E-mail: a.n.kislov@urfu.ru; Zatsepin, A. F., E-mail: a.n.kislov@urfu.ru [Ural Federal University, 19 Mira St., Yekaterinburg, 620002 (Russian Federation)
2014-10-21T23:59:59.000Z
Atomic structure and localized vibrations of ??SiO{sub 2}:Ge are studied using computer modeling techniques. The simulation was carried out by the lattice dynamics calculation of the local density of vibrational states. Local structures parameters are calculated, localized symmetrized vibrations frequency caused by Ge impurity in different charge states are defined. The movements of atoms located near Ge impurity are analyzed and their contribution into localized vibrations of different type is evaluated.
Improve Claus simulation by integrating kinetic limitations into equilibrium calculations
Wen, T.C.
1986-01-01T23:59:59.000Z
Since all existing Claus simulators are based on equilibrium calculations, it is not surprising that the simulation results, including the overall sulfur yield, air to acid gas ratio, and stream compositions are somewhat different from the plant data. One method for improving the simulation is to consider the kinetic limitations in the Claus reactions. This has been accomplished in this work by integrating kinetic considerations into equilibrium calculations. Kinetic limitations have been introduced in both the Claus reaction furnace and the catalytic converters. An interactive computer program SULPLT Version 3 was written to implement the proposed modifications. The computer program was used to simulate the Claus furnace, catalytic converters, and the effect of air to acid gas ratio on sulfur recovery to check against literature data. Three Claus plants for which data exist have also been simulated. The results show that the proposed model predicts sulfur recovery, sulfur emission, optimal air to acid gas ratio, and various stream compositions more accurately than the equilibrium model. The proposed model appears to be valid, reliable, and applicable over a wide range of operating conditions (acid gas feeds ranging from 13% to 95% H/sub 2/S with different levels of impurities). The methodology developed in this study should be applicable to any reaction systems where kinetic limitations are important but where equilibrium still prevails.
Mass Insertions vs. Mass Eigenstates calculations in Flavour Physics
Dedes, A; Rosiek, J; Suxho, K; Tamvakis, K
2015-01-01T23:59:59.000Z
We present and prove a theorem of matrix analysis, the Flavour Expansion Theorem (or FET), according to which, an analytic function of a Hermitian matrix can be expanded polynomially in terms of its off-diagonal elements with coefficients being the divided differences of the analytic function and arguments the diagonal elements of the Hermitian matrix. The theorem is applicable in case of flavour changing amplitudes. At one-loop level this procedure is particularly natural due to the observation that every loop function in the Passarino-Veltman basis can be recursively expressed in terms of divided differences. FET helps to algebraically translate an amplitude written in mass eigenbasis into flavour mass insertions, without performing diagrammatic calculations in flavour basis. As a non-trivial application of FET up to a third order, we demonstrate its use in calculating strong bounds on the real parts of flavour changing mass insertions in the up- squark sector of the MSSM from neutron Electric Dipole Moment...
Criticality calculations for Step-2 GPHS modules.
Hensen, Danielle Lynn; Lipinski, Ronald J.
2007-08-01T23:59:59.000Z
The Multi-Mission Radioisotope Thermoelectric Generator (MMRTG) will use an improved version of the General Purpose Heat Source (GPHS) module as its source of thermal power. This new version, referred to as the Step-2 GPHS Module, has additional and thicker layers of carbon fiber material (Fine Weaved Pierced Fabric) for increased strength over the original GPHS module. The GPHS uses alpha decay of {sup 238}Pu in the oxide form as the primary source of heat, and small amounts of other actinides are also present in the oxide fuel. Criticality calculations have been performed by previous researchers on the original version of the GPHS module (Step 0). This paper presents criticality calculations for the present Step-2 version. The Monte Carlo N-Particle eXtended code (MCNPX) was used for these calculations. Numerous configurations of GPHS module arrays surrounded by wet sand and other materials (to reflect the neutrons back into the stack with minimal absorption) were modeled. For geometries with eight GPHS modules (from a single MMRTG) surrounded by wet sand, the configuration is extremely sub-critical; k{sub eff} is about 0.3. It requires about 1000 GPHS modules (from 125 MMRTGs) in a close-spaced stack to approach criticality (k{sub eff} = 1.0) when surrounded by wet sand. The effect of beryllium in the MMRTG was found to be relatively small.
Criticality Calculations for Step-2 GPHS Modules
Lipinski, Ronald J. [Advanced Nuclear Concepts Department, Sandia National Laboratories, P.O Box 5800, Albuquerque, NM 87185 (United States); Hensen, Danielle L. [Risk and Reliability Department Sandia National Laboratories, P.O Box 5800, Albuquerque, NM 87185 (United States)
2008-01-21T23:59:59.000Z
The Multi-Mission Radioisotope Thermoelectric Generator (MMRTG) will use an improved version of the General Purpose Heat Source (GPHS) module as its source of thermal power. This new version, referred to as the Step-2 GPHS Module, has additional and thicker layers of carbon fiber material (Fine Weaved Pierced Fabric) for increased strength over the original GPHS module. The GPHS uses alpha decay of {sup 238}Pu in the oxide form as the primary source of heat, and small amounts of other actinides are also present in the oxide fuel. Criticality calculations have been performed by previous researchers on the original version of the GPHS module (Step 0). This paper presents criticality calculations for the present Step-2 version. The Monte Carlo N-Particle eXtended code (MCNPX) was used for these calculations. Numerous configurations of GPHS module arrays surrounded by wet sand and other materials (to reflect the neutrons back into the stack with minimal absorption) were modeled. For geometries with eight GPHS modules (from a single MMRTG) surrounded by wet sand, the configuration is extremely sub-critical; k{sub eff} is about 0.3. It requires about 1000 GPHS modules (from 125 MMRTGs) in a close-spaced stack to approach criticality (k{sub eff} = 1.0) when surrounded by wet sand. The effect of beryllium in the MMRTG was found to be relatively small.
Cosmology calculations almost without general relativity
Thomas F. Jordan
2004-12-08T23:59:59.000Z
The Friedmann equation is derived for a Newtonian universe. Changing mass density to energy density gives exactly the Friedmann equation of general relativity. Accounting for work done by pressure then yields the two Einstein equations that govern the expansion of the universe. Descriptions and explanations of radiation pressure and vacuum pressure are added to complete a basic kit of cosmology tools. It provides a basis for teaching cosmology to undergraduates in a way that quickly equips them to do basic calculations. This is demonstrated with calculations involving: characteristics of the expansion for densities dominated by radiation, matter, or vacuum; the closeness of the density to the critical density; how much vacuum energy compared to matter energy is needed to make the expansion accelerate; and how little is needed to make it stop. Travel time and luninosity distance are calculated in terms of the redshift and the densities of matter and vacuum energy, using a scaled Friedmann equation with the constant in the curvature term determined by matching with the present values of the Hubble parameter and energy density. General relativity is needed only for the luminosity distance, to describe how the curvature of space, determined by the energy density, can change the intensity of light by changing the area of the sphere to which the light has spread. Thirty-one problems are included.
The Filter Difference Spectrometer
Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)
Difference Spectrometer (FDS) is used for molecular vibrational spectroscopy by inelastic neutron scattering. The instrument is designed for high count rates by use of large...
Abdel-Khalik, Hany S.; Gardner, Robin; Mattingly, John; Sood, Avneet
2014-05-20T23:59:59.000Z
The development of hybrid Monte-Carlo-Deterministic (MC-DT) approaches, taking place over the past few decades, have primarily focused on shielding and detection applications where the analysis requires a small number of responses, i.e. at the detector locations(s). This work further develops a recently introduced global variance reduction approach, denoted by the SUBSPACE approach is designed to allow the use of MC simulation, currently limited to benchmarking calculations, for routine engineering calulations. By way of demonstration, the SUBSPACE approach is applied to assembly level calculations used to generate the few-group homogenized cross-sections. These models are typically expensive and need to be executed in the order of 10-10 times to properly characterize the few-group cross-sections for deownstream core-wide calculations. Applicability to k-eigenvalue core-wide models is also demonstrated in this work. Given the faborable results obtained in this work, we believe the applicability of the MC method for reactor analysis calculations could be realized in the near future.
NSRD-2015-TD01, Technical Report for Calculations of Atmospheric...
Office of Environmental Management (EM)
NSRD-2015-TD01, Technical Report for Calculations of Atmospheric Dispersion at Onsite Locations for DOE Nuclear Facilities NSRD-2015-TD01, Technical Report for Calculations of...
First-principles calculations of the electronic structure, phase...
Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)
calculations of the electronic structure, phase transition and properties of ZrSiO4 polymorphs. First-principles calculations of the electronic structure, phase transition and...
Building America Webinar: HVAC Right-Sizing Part 1-Calculating...
HVAC Right-Sizing Part 1-Calculating Loads Building America Webinar: HVAC Right-Sizing Part 1-Calculating Loads During this webinar, Building America Research Team IBACOS...
Measurement and Verification Plan and Savings Calculations Methods...
Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site
Measurement and Verification Plan and Savings Calculations Methods Outline (IDIQ Attachment J-8) Measurement and Verification Plan and Savings Calculations Methods Outline (IDIQ...
Yerokhin, V A; Fritzsche, S
2014-01-01T23:59:59.000Z
We perform relativistic configuration-interaction calculations of the energy levels of the low-lying and core-excited states of beryllium-like iron, Fe$^{22+}$. The results include the QED contributions calculated by two different methods, the model QED operator approach and the screening-potential approach. The uncertainties of theoretical energies are estimated systematically. The predicted wavelengths of the K\\alpha transitions in beryllium-like iron improve previous theoretical results and compare favorably with the experimental data.
Calculations of dynamic stresses in the envelopes of pulsed Xe flashlamps
Holdener, F.R.; Platt, E.A.; Erlandson, A.C.; Frank, D.N.; Gelinas, R.J.; Jancaitis, K.S.; Larson, D.W.; Sinz, K.H.
1992-08-31T23:59:59.000Z
We have modeled dynamic stresses in the envelopes of pulsed xenon flashlamps, treating stresses produced by three different sources: the heating of the envelope by the plasma; the pressure rise of the xenon gas; and magnetic forces, due to currents flowing in nearby lamps. The heat-induced stresses were calculated by the finite element method, using uniform heating rates for the inside surface of the envelope that were inferred from flashlamp radiant efficiency measurements. Pressure-induced stresses were calculated analytically, using empirical relationships for temperature and pressure in terms of current density. Magnetically-induced stresses were also calculated analytically, for flashlamps packed parallel to each other in linear arrays.
Excited state contamination in nucleon structure calculations
Jeremy Green; Stefan Krieg; John Negele; Andrew Pochinsky; Sergey Syritsyn
2011-11-28T23:59:59.000Z
Among the sources of systematic error in nucleon structure calculations is contamination from unwanted excited states. In order to measure this systematic error, we vary the operator insertion time and source-sink separation independently. We compute observables for three source-sink separations between 0.93 fm and 1.39 fm using clover-improved Wilson fermions and pion masses as low as 150 MeV. We explore the use of a two-state model fit to subtract off the contribution from excited states.
Calculation of Neutral Beam Injection into SSPX
Pearlstein, L D; Casper, T A; Hill, D N; LoDestro, L L; McLean, H S
2006-06-13T23:59:59.000Z
The SSPX spheromak experiment has achieved electron temperatures of 350eV and confinement consistent with closed magnetic surfaces. In addition, there is evidence that the experiment may be up against an operational beta limit for Ohmic heating. To test this barrier, there are firm plans to add two 0.9MW Neutral Beam (NB) sources to the experiment. A question is whether the limit is due to instability. Since the deposited Ohmic power in the core is relatively small the additional power from the beams is sufficient to significantly increase the electron temperature. Here we present results of computations that will support this contention. We have developed a new NB module to calculate the orbits of the injected fast fast-ions. The previous computation made heavy use of tokamak ordering which fails for a tight-aspect-ratio device, where B{sub tor} {approx} B{sub pol}. The model calculates the deposition from the NFREYA package [1]. The neutral from the CX deposition is assumed to be ionized in place, a high-density approximation. The fast ions are then assumed to fill a constant angular momentum orbit. And finally, the fast ions immediately assume the form of a dragged down distribution. Transfer rates are then calculated from this distribution function [2]. The differential times are computed from the orbit times and the particle weights in each flux zone (the sampling bin) are proportional to the time spent in the zone. From this information the flux-surface-averaged profiles are obtained and fed into the appropriate transport equation. This procedure is clearly approximate, but accurate enough to help guide experiments. A major advantage is speed: 5000 particles can be processed in under 4s on our fastest LINUX box. This speed adds flexibility by enabling a ''large'' number of predictive studies. Similar approximations, without the accurate orbit calculation presented here, had some success comparing with experiment and TRANSP [3]. Since our procedure does not have multiple CX and relies on disparate time scales, more detailed understanding requires a ''complete'' NB package such as the NUBEAM [4] module, which follows injected fast ions along with their generations until they enter the main thermal distribution.
Calculator program trilogy characterizes comingled gas streams
Flowers, R.
1985-08-26T23:59:59.000Z
A series of programs has been developed for the HP-41CV that allows a quicker and more accurate approach to commingled stream calculations. This avoids the margin of error that the representative method introduces. The alpha-numeric capability of the HP-41CV will prompt for the inputs of an 11-component stream. The program series comprises: gas analysis; gas gathering/gas analysis; and flash vaporization. Each of these programs has its stand-alone use; but their true worth is in their integrated capability.
Simple method for calculating island widths
Cary, J.R.; Hanson, J.D.; Carreras, B.A.; Lynch, V.E.
1989-01-01T23:59:59.000Z
A simple method for calculating magnetic island widths has been developed. This method uses only information obtained from integrating along the closed field line at the island center. Thus, this method is computationally less intensive than the usual method of producing surfaces of section of sufficient detail to locate and resolve the island separatrix. This method has been implemented numerically and used to analyze the buss work islands of ATF. In this case the method proves to be accurate to at least within 30%. 7 refs.
Simple method for calculating island widths
Cary, J.R. (Department of Astrophysical, Planetary, and Atmospheric Sciences, and Department of Physics, University of Colorado, Boulder, Colorado 80309-0391 (USA)); Hanson, J.D. (Department of Physics, Auburn University, Auburn, Alabama 36849 (USA))
1991-04-01T23:59:59.000Z
A simple method for calculating magnetic island widths has been developed. This method uses only that information obtained from integrating along the closed field line at the island center. Thus, this method is computationally less intensive than the usual method of producing surfaces of section of sufficient detail to locate and resolve the island separatrix. This method has been implemented numerically and used to analyze the buss work islands of ATF (Fusion Technol. {bold 10}, 179 (1986)). In this case the method proves to be accurate to at least within 20% even though the islands are within a factor of 2 of overlapping.
Hybrid Car Calculator | Open Energy Information
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AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand JumpConceptual Model, clickInformationNew| Exploration Technique:Illinois: EnergyRoof Calculator
Multicavity SCRF calculation of ion hydration energies
Diercksen, B.H.F. [Max-Planck-Institut Fuer Astrophysik, Muenchen (Germany); Karelson, M. [Univ. of Tartu (Estonia); Tamm, T. [Univ. of Florida, Gainesville, FL (United States)
1994-12-31T23:59:59.000Z
The hydration energies of the proton, hydroxyl ion, and several inorganic ions were calculated using the multicavity self-consistent reaction field (MCa SCRF) method developed for the quantum-mechanical modeling of rotationally or flexible systems in dielectric media. The ionic complexes H{sub 3}O{sup +}(H2O){sub 4}, OH{sup {minus}}(H2O){sub 4}, NH{sup +}{sub 4}(H2O){sub 4}, and Hal{sup {minus}}(H2O){sub 4}, where Hal = F, Cl, or Br, have been studied. Each complex was divided between five spheres, corresponding to the central ion and four water molecules in their first coordination sphere, respectively. Each cavity was surrounded by a polarizable medium with the dielectric permittivity of water at room temperature (80). The ionic hydration energies of ions were divided into specific and nonspecific parts. After accounting for the cavity-formation energy using scaled particle theory, good agreement between the total calculated and experimental hydration energies was obtained for all ions studied.
Consistent neutron kinetics data generation for nodal transient calculations
Akdeniz, B. [Penn State Univ., Nuclear Engineering Program, Univ. Park, PA 16802 (United States); Mueller, E.; Panayotov, D. [Westinghouse Electric Sweden, SE - 721 63 Vaesteraas (Sweden); Ivanov, K. N. [Penn State Univ., Nuclear Engineering Program, Univ. Park, PA 16802 (United States)
2006-07-01T23:59:59.000Z
Current three-dimensional transient codes for thermal reactors are mostly based on two-group diffusion-theory nodal models. In the two-group approach no explicit distinction is made between prompt fission neutrons and delayed neutrons. Consequently, effective delayed neutron fractions have traditionally been used in an attempt to compensate for this shortcoming. A fundamentally better approach would be to solve the nodal kinetics equations in a sufficient number of energy groups to explicitly capture neutron emission spectrum effects. However, this would require the availability of a multi-group nodal transient code as well as a lattice code to generate the appropriate multi-group nodal data for the simulator. One such simulator is the PARCS nodal transient code, which is widely used and recognized as representative of the current state-of-the-art. Unfortunately, a proper nodal data preparation path between PARCS and a lattice code is not available. Even though several industrial lattice codes could be considered as candidates, most of them are tailored to producing two-group nodal data and would require modifications to produce multi-group prompt and delayed neutron emission spectra. In this paper, the particular modifications required to match the TransLAT lattice code and the PARCS nodal transient code for BWR transient applications are reported. Some modifications to PARCS were also required to make two-group and multi-group applications fully consistent. Numerical results are presented both to verify the proper functioning of these modifications and to illuminate the impact of various nodal kinetics data approximations in a selected transient calculation. In particular, the significance of blending rodded and un-rodded kinetics data in partially rodded nodes is demonstrated. It is also confirmed that the use of delayed neutron importance factors in two-group calculations notably reduces the differences between two-group and multi-group kinetics calculations. (authors)
Johnson, Eric E.
PV modules, with a life measured in decades, will typically be in place longer than the outdoor and repaired promptly. PV systems suffer gradual degradation that is often not monitored, and the PV array may with copper conductors. On the other hand, PV systems have numerous modules (tens to thousands) and mounting
Liu, M.; Zheng, K.; Wu, L.; Wang, Z.; Johnson, C.
2007-01-01T23:59:59.000Z
. In this part, a simulated air handling unit (AHU) system in Omaha NE is used to demonstrate the energy savings performance in one typical climate year. This AHU system has a static pressure reset system and two constant static pressure systems, one having...
Corrosion of reinforcing steel is typically one of the main problems causing deterioration available steel, has proven to have high corrosion resistance in comparison with conventional steel without provides a high resistance to corrosion due to severe environmental exposure in comparison to the use
Lucas, Robert G.; Mendon, Vrushali V.; Goel, Supriya
2012-06-01T23:59:59.000Z
The 2009 and 2012 International Energy Conservation Codes (IECC) require a substantial improvement in energy efficiency compared to the 2006 IECC. This report averages the energy use savings for a typical new residential dwelling unit based on the 2009 and 2012 IECC compared to the 2006 IECC. Results are reported by the eight climate zones in the IECC and for the national average.
Random number stride in Monte Carlo calculations
Hendricks, J.S.
1990-01-01T23:59:59.000Z
Monte Carlo radiation transport codes use a sequence of pseudorandom numbers to sample from probability distributions. A common practice is to start each source particle a predetermined number of random numbers up the pseudorandom number sequence. This number of random numbers skipped between each source particles the random number stride, S. Consequently, the jth source particle always starts with the j{center dot}Sth random number providing correlated sampling'' between similar calculations. A new machine-portable random number generator has been written for the Monte Carlo radiation transport code MCNP providing user's control of the random number stride. First the new MCNP random number generator algorithm will be described and then the effects of varying the stride will be presented. 2 refs., 1 fig.
On the calculation of mutual information
Duncan, Tyrone E.
1970-07-01T23:59:59.000Z
as follows: (1) d Yt Zt dt + dBt, where the n-dimensional process Z is independent of the n-dimensional standard Brownian motion B, [0, 1], Yo =- 0 and (2) f,f ZTt Zt dP dr< where the superscript T denotes transpose. We wish to calculate the amount... was supported by the United States Air Force under Grant AF-AFOSR 814-66. 215 D ow nl oa de d 09 /1 0/ 14 to 1 29 .2 37 .4 6. 10 0. R ed ist rib ut io n su bje ct to SIA M lic en se or co py rig ht; se e h ttp ://w ww .si am .or g/j ou rna ls/ ojs a...
A primer for criticality calculations with DANTSYS
Busch, R.D. [Univ. of New Mexico, Albuquerque, NM (United States). Nuclear Criticality Safety Group
1997-08-01T23:59:59.000Z
With the closure of many experimental facilities, the nuclear safety analyst has to rely on computer calculations to identify safe limits for the handling and storage of fissile materials. Although deterministic methods often do not provide exact models of a system, a substantial amount of reliable information on nuclear systems can be obtained using these methods if the user understands their limitations. To guide criticality specialists in this area, the Nuclear Criticality Safety Group at the University of New Mexico (UNM) in cooperation with the Radiation Transport Group at Los Alamos National Laboratory (LANL) has designed a primer to help the analyst understand and use the DANTSYS deterministic transport code for nuclear criticality safety analyses. DANTSYS is the new name of the group of codes formerly known as: ONEDANT, TWODANT, TWOHEX, TWOGQ, and THREEDANT. The primer is designed to teach bu example, with each example illustrating two or three DANTSYS features useful in criticality analyses. Starting with a Quickstart chapter, the primer gives an overview of the basic requirements for DANTSYS input and allows the user to quickly run a simple criticality problem with DANTSYS. Each chapter has a list of basic objectives at the beginning identifying the goal of the chapter and the individual DANTSYS features covered in detail in the chapter example problems. On completion of the primer, it is expected that the user will be comfortable doing criticality calculations with DANTSYS and can handle 60--80% of the situations that normally arise in a facility. The primary provides a set of input files that can be selective modified by the user to fit each particular problem.
RELAP5 posttest calculation of IAEA-SPE-4
Petelin, S.; Mavko, B.; Parzer, I.; Prosek, A.
1994-12-31T23:59:59.000Z
The International Atomic Energy Agency`s Fourth Standard Problem Exercise (IAEA-SPE-4) was performed at the PMK-2 facility. The PMK-2 facility is designed to study processes following small- and medium-size breaks in the primary system and natural circulation in VVER-440 plants. The IAEA-SPE-4 experiment represents a cold-leg side small break, similar to the IAEA-SPE-2, with the exception of the high-pressure safety injection being unavailable, and the secondary side bleed and feed initiation. The break valve was located at the dead end of a vertical downcomer, which in fact simulates a break in the reactor vessel itself, and should be unlikely to happen in a real nuclear power plant (NPP). Three different RELAP5 code versions were used for the transient simulation in order to assess the calculations with test results.
Song, Xueyu
Accurate method to calculate liquid and solid free energies for embedded atom potentials Xueyu Song system we have directly calculated free energies of fluid and solid phases of aluminum with an embedded simulations. Moreover, the free energies of the two different phases are calculated in a single approach
Different Approach to the Aluminium Oxide Topography Characterisation
Poljacek, Sanja Mahovic; Gojo, Miroslav [Faculty of Graphic Arts, University of Zagreb, Getaldiceva 2, 10000 Zagreb (Croatia); Raos, Pero; Stoic, Antun [Mechanical Engineering Faculty, J.J. Strossmayer University of Osijek, Trg Ivane Brlic Mazuranic 2, 35000 Slavonski Brod (Croatia)
2007-04-07T23:59:59.000Z
Different surface topographic techniques are being widely used for quantitative measurements of typical industrial aluminium oxide surfaces. In this research, specific surface of aluminium oxide layer on the offset printing plate has been investigated by using measuring methods which have previously not been used for characterisation of such surfaces. By using two contact instruments and non-contact laser profilometer (LPM) 2D and 3D roughness parameters have been defined. SEM micrographs of the samples were made. Results have shown that aluminium oxide surfaces with the same average roughness value (Ra) and mean roughness depth (Rz) typically used in the printing plate surface characterisation, have dramatically different surface topographies. According to the type of instrument specific roughness parameters should be used for defining the printing plate surfaces. New surface roughness parameters were defined in order to insure detailed characterisation of the printing plates in graphic reproduction process.
Hong, Tianzhen
2009-01-01T23:59:59.000Z
consisting of a water heater tank, a direct expansion (DX) “many types of water heaters and storage tanks, including gasIndirect Tank loss calculations are different Water Heaters
Variations in gear fatigue life for different wind turbine braking strategies
McNiff, B.P. (Second Wind, Inc., Somerville, MA (USA)); Musial, W.D. (Solar Energy Research Inst., Golden, CO (USA)); Errichello, R. (GEARTECH, Albany, CA (USA))
1991-06-01T23:59:59.000Z
A large number of gearbox failures have occurred in the wind industry in a relatively short period, many because service loads were underestimated. High-torque transients that occur during starting and stopping are difficult to predict and may be overlooked in specifying gearbox design. Although these events comprise a small portion of total load cycles, they can be the most damaging. The severity of these loads varies dramatically with the specific configuration of the wind turbine. The large number of failures in Danish-designed Micon 65 wind turbines prompted this investigation. The high-speed and low-speed shaft torques were measured on a two-stage helical gearbox of a single Micon 65 turbine. Transient events and normal running loads were combined statistically to obtain a typical annual load spectrum. The pitting and bending fatigue lives of the gear teeth were calculated by using Miner's rule for four different high-speed shaft brake configurations. Each breaking scenario was run for both a high- and a low-turbulence normal operating load spectrum. The analysis showed increases in gear life by up to a factor of 25 when the standard high-speed shaft brake is replaced with a dynamic brake or modified with a damper. 9 refs., 9 figs., 3 tabs.
Barbaras, Sean A. [United States Military Academy, West Point, New York 10996 (United States); Knight, Travis W. [University of South Carolina, Columbia, South Carolina 29208 (United States)
2012-07-01T23:59:59.000Z
Using Mixed Oxide (MOX) fuel in traditional Pressurized Water Reactor (PWR) assemblies has been researched at length and has shown to provide the benefit of transmutation and targets the amount and toxicity of high level waste needed to be managed. Advanced MOX concepts using enriched Uranium Dioxide (UO{sub 2}) are required for multiple recycling of plutonium. The use of MOX and ordinary UO{sub 2} fuel in the same assembly as well as unfueled rods and assembly edge effects contrasts with the unit cell computational assumption of a uniform infinite array of rods. While a deterministic method of calculating the Dancoff factor has traditionally been employed in fuel assembly analysis due to the lighter computational and modeling requirements, this research seeks to determine the validity of the uniform, infinite lattice assumption with respect to Dancoff factor and determine the magnitude of the impact of nonuniform lattice effects on fuel assembly criticality calculations as well as transuranic isotope production and transmutation. This research explored the pin-to-pin interaction in a non-uniform lattice of MOX fuel rods and UO{sub 2} fuel rods through the impact of the calculated Dancoff factors from the deterministic method used in SCALE versus the Monte Carlo method used in the code DANCOFF-MC. Using the Monte Carlo method takes into account the non-uniform lattice effects of having neighboring fuel rods with different cross-sectional spectra whereas the Dancoff factor calculated by SCALE assumes a uniform, infinite lattice of one fuel rod type. Differences in eigenvalue calculations as a function of burnup are present between the two methods of Dancoff factor calculation. The percent difference is greatest at low burnup and then becomes smaller throughout the cycle. Differences in the transmutation rate of transuranic isotopes in the MOX fuel are also present between the Dancoff factor calculation methods. The largest difference is in Pu-239, Pu-242, and Am-241 composition whereas U-238, Pu-242, and Pu-238 composition was not changed by taking into account the non-homogenous lattice effects. Heterogeneous lattice effects do change the calculated eigenvalue and transmutation rate in a non-uniform lattice of MOX fuel rods and UO{sub 2} fuel. However, the uncertainty in the ENDF data used by SCALE in these calculations is large enough that the infinite lattice assumption remains valid. (authors)
Development of a Roof Savings Calculator
New, Joshua Ryan [ORNL] [ORNL; Miller, William A [ORNL] [ORNL; Desjarlais, Andre Omer [ORNL] [ORNL; Erdem, Ender [Lawrence Berkeley National Laboratory (LBNL)] [Lawrence Berkeley National Laboratory (LBNL); Huang, Joe [Lawrence Berkeley National Laboratory (LBNL)] [Lawrence Berkeley National Laboratory (LBNL)
2011-01-01T23:59:59.000Z
A web-based Roof Savings Calculator (RSC) has been deployed for the Department of Energy as an industry-consensus tool to help building owners, manufacturers, distributors, contractors and researchers easily run complex roof and attic simulations. This tool employs the latest web technologies and usability design to provide an easy input interface to an annual simulation of hour-by-hour, whole-building performance using the world-class simulation tools DOE-2.1E and AtticSim. Building defaults were assigned and can provide estimated annual energy and cost savings after the user selects nothing more than building location. In addition to cool reflective roofs, the RSC tool can simulate multiple roof types at arbitrary inclinations. There are options for above sheathing ventilation, radiant barriers, and low-emittance surfaces. The tool also accommodates HVAC ducts either in the conditioned space or in the attic with custom air leakage rates. Multiple layers of building materials, ceiling and deck insulation, and other parameters can be compared side-by-side to generate an energy/cost savings estimate between two buildings. The RSC tool was benchmarked against field data for demonstration homes in Ft. Irwin, CA.
Development of a Roof Savings Calculator
New, Joshua Ryan [ORNL] [ORNL; Miller, William A [ORNL] [ORNL; Huang, Joe [Lawrence Berkeley National Laboratory (LBNL)] [Lawrence Berkeley National Laboratory (LBNL); Erdem, Ender [Lawrence Berkeley National Laboratory (LBNL)] [Lawrence Berkeley National Laboratory (LBNL)
2011-01-01T23:59:59.000Z
A web-based Roof Savings Calculator (RSC) has been deployed for the Department of Energy as an industry-consensus tool to help building owners, manufacturers, distributors, contractors and researchers easily run complex roof and attic simulations. This tool employs the latest web technologies and usability design to provide an easy input interface to an annual simulation of hour-by-hour, whole-building performance using the world-class simulation tools DOE-2.1E and AtticSim. Building defaults were assigned and can provide annual energy and cost savings after the user selects nothing more than building location. In addition to cool reflective roofs, the RSC tool can simulate multiple roof types at arbitrary inclinations. There are options for above sheathing ventilation, radiant barriers and low-emittance surfaces. The tool also accommodates HVAC ducts either in the conditioned space or in the attic with custom air leakage rates. Multiple layers of thermal mass, ceiling insulation and other parameters can be compared side-by-side to generate energy/cost savings between two buildings. The RSC tool was benchmarked against field data for demonstration homes in Ft Irwin, CA.
Available Energy Calculations for Process Engineers
Parker, A. L.
1982-01-01T23:59:59.000Z
in the unit plus the difference in the free energy of mixing for the unit feed and product streams at dead state condi tions. Thus, by a proper choice of reference state, lost work values may be computed without defining a reference environment... pressure decreases. Available Energy Analysis Via Computer Virtually every major design and most minor designs done today are, at one time or another, modeled with a steady state chemical process simulator such as ASPEN (8 and 9), Monsantos' FLOWTRAN...
TTDTTC^/TTN MS#-R-68I Danish Calculations of
»Reactor« Calculations on Assembly Basis 10 3.4 Fin Power Reconstruction 11 4Res*ks 13 4.1 Cl;1 Introduction Thebenchmark is described in NEACRP-L-33*. Så efferent .reactor, coo- figwations are considered,which togetherwith a numberofcodes based on different principles (nodal expansion, nKshcenocs or mesh coroen bawd
An enhanced model for calculating delay as a function of offset
Jain, Shweta
1996-01-01T23:59:59.000Z
This thesis presents the enhancements made to an existing model for calculating delay as a function of offset between the traffic signals of a link. The delay-difference-of offset technique is a signal control concept used for strategic optimization...
First-principles calculations of step formation energies and step interactions on TiN(001)
Ciobanu, Cristian
First-principles calculations of step formation energies and step interactions on TiN(001) Cristian the formation energies and repulsive interactions of monatomic steps on the TiN(001) surface, using den- sity studies on different aspects related to thin film growth on TiN surfaces, few atomistic studies have been
Pasterski, Vickie; Acerini, Carlo L.; Dunger, David B.; Ong, Ken K.; Hughes, Ieuan A.; Thankamony, Ajay; Hines, Melissa
2015-01-15T23:59:59.000Z
it remains until puberty (Achermann and Hadders-Algra, 2006). Though these parallel proce terized, their potential behavioral consequences, postnatal period, have yet to be fully understood. Experimental studies of rats and non-humanp exposure during... –192. Constantinescu, M., Hines, M., 2012. Relating prenatal testosterone exposure to postnatal be- havior in typically developing children: methods and findings. Child Dev. Perspect. 1–7. de Graaf-Peters, V.B., Hadders-Algra, M., 2006. Ontogeny of the human central...
Hyperon Puzzle: Hints from Quantum Monte Carlo Calculations
Diego Lonardoni; Alessandro Lovato; Stefano Gandolfi; Francesco Pederiva
2015-02-27T23:59:59.000Z
The onset of hyperons in the core of neutron stars and the consequent softening of the equation of state have been questioned for a long time. Controversial theoretical predictions and recent astrophysical observations of neutron stars are the grounds for the so-called hyperon puzzle. We calculate the equation of state and the neutron star mass-radius relation of an infinite systems of neutrons and $\\Lambda$ particles by using the auxiliary field diffusion Monte Carlo algorithm. We find that the three-body hyperon-nucleon interaction plays a fundamental role in the softening of the equation of state and for the consequent reduction of the predicted maximum mass. We have considered two different models of three-body force that successfully describe the binding energy of medium mass hypernuclei. Our results indicate that they give dramatically different results on the maximum mass of neutron stars, not necessarily incompatible with the recent observation of very massive neutron stars. We conclude that stronger constraints on the hyperon-neutron force are necessary in order to properly assess the role of hyperons in neutron stars.
BENCHMARKING UPGRADED HOTSPOT DOSE CALCULATIONS AGAINST MACCS2 RESULTS
Brotherton, Kevin
2009-04-30T23:59:59.000Z
The radiological consequence of interest for a documented safety analysis (DSA) is the centerline Total Effective Dose Equivalent (TEDE) incurred by the Maximally Exposed Offsite Individual (MOI) evaluated at the 95th percentile consequence level. An upgraded version of HotSpot (Version 2.07) has been developed with the capabilities to read site meteorological data and perform the necessary statistical calculations to determine the 95th percentile consequence result. These capabilities should allow HotSpot to join MACCS2 (Version 1.13.1) and GENII (Version 1.485) as radiological consequence toolbox codes in the Department of Energy (DOE) Safety Software Central Registry. Using the same meteorological data file, scenarios involving a one curie release of {sup 239}Pu were modeled in both HotSpot and MACCS2. Several sets of release conditions were modeled, and the results compared. In each case, input parameter specifications for each code were chosen to match one another as much as the codes would allow. The results from the two codes are in excellent agreement. Slight differences observed in results are explained by algorithm differences.
Napier, B.A.
1992-12-01T23:59:59.000Z
A series of scoping calculations has been undertaken to evaluate the absolute and relative contributions of different radionuclides and exposure pathways to doses that may have been received by individuals living in the vicinity of the Hanford Site. This scoping calculation (Calculation 004) examined the contributions of numerous radionuclides to cumulative dose via environmental exposures and accumulation in foods. Addressed in this calculation were the contributions to organ and effective dose of infants and adults from (1) air submersion and groundshine external dose, (2) inhalation, (3) ingestion of soil by humans, (4) ingestion of leafy vegetables, (5) ingestion of other vegetables and fruits, (6) ingestion of meat, (7) ingestion of eggs, and (8) ingestion of cows` milk from Feeding Regime 1, as described in calculation 002. This calculation specifically addresses cumulative radiation doses to infants and adults resulting from releases occurring over the period 1945 through 1972.
Supporting Calculations For Submerged Bed Scrubber Condensate Disposal Preconceptual Study
Pajunen, A. J.; Tedeschi, A. R.
2012-09-18T23:59:59.000Z
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.
Normalizing Weather Data to Calculate Energy Savings Peer Exchange...
Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site
Normalizing Weather Data to Calculate Energy Savings Peer Exchange Call Normalizing Weather Data to Calculate Energy Savings Peer Exchange Call February 26, 2015 3:00PM to 4:3...
Helium release rates and ODH calculations from RHIC magnet cooling line failure
Liaw, C.J.; Than, Y.; Tuozzolo, J.
2011-03-28T23:59:59.000Z
A catastrophic failure of the magnet cooling lines, similar to the LHC superconducting bus failure incident, could discharge cold helium into the RHIC tunnel and cause an Oxygen Deficiency Hazard (ODH) problem. A SINDA/FLUINT{reg_sign} model, which simulated the 4.5K/4 atm helium flowing through the magnet cooling system distribution lines, then through a line break into the insulating vacuum volumes and discharging via the reliefs into the RHIC tunnel, had been developed. Arc flash energy deposition and heat load from the ambient temperature cryostat surfaces are included in the simulations. Three typical areas: the sextant arc, the Triplet/DX/D0 magnets, and the injection area, had been analyzed. Results, including helium discharge rates, helium inventory loss, and the resulting oxygen concentration in the RHIC tunnel area, are reported. Good agreement had been achieved when comparing the simulation results, a RHIC sector depressurization test measurement, and some simple analytical calculations.
Verweij, A
2006-01-01T23:59:59.000Z
CUDI is the extended Fortran code to calculate the electrodynamic and thermal behaviour of any type of Rutherford cable subject to global and/or local variations in field, transport current, and external heat release. The internal parameters of the cable can be freely varied along the length and across the width, such as contact resistances, critical current, cooling rates etc. In this way, all the typical non-uniformities occurring in a cable, e.g. broken filaments, strand welds, cable joints, and edge degradation can be simulated. Also the characteristics of the strands in the cable can be varied from strand to strand. Heat flows through the matrix, through the interstrand contacts, and to the helium are incorporated, as well as the self-field and self- and mutual inductances between the strands. The main features and structure of the program will be discussed.
TDHF fusion calculations for spherical+deformed systems
A. S. Umar; V. E. Oberacker
2006-04-04T23:59:59.000Z
We outline a formalism to carry out TDHF calculations of fusion cross sections for spherical + deformed nuclei. The procedure incorporates the dynamic alignment of the deformed nucleus into the calculation of the fusion cross section. The alignment results from multiple E2/E4 Coulomb excitation of the ground state rotational band. Implications for TDHF fusion calculations are discussed. TDHF calculations are done in an unrestricted three-dimensional geometry using modern Skyrme force parametrizations.
SCHWARTZ,S.E.
2000-09-21T23:59:59.000Z
It is no longer appropriate, if it ever was, to think of atmospheric aerosols as homogeneous spheres of uniform composition and size. Within the United States, and even more globally, not only the mass loading but also the composition, morphology, and size distribution of atmospheric aerosols are highly variable, as a function of location, and at a given location as a function of time. Particles of a given aerodynamic size may differ from one another, and even within individual particles material may be inhomogeneously distributed, as for example, carbon spherules imbedded in much larger sulfate particles. Some of the particulate matter is primary, that is, introduced into the atmosphere directly as particles, such as carbon particles in diesel exhaust. Some is secondary, that is, formed in the atmosphere by gas-to-particle conversion. Much of the material is inorganic, mainly sulfates and nitrates resulting mainly from energy-related emissions. Some of the material is carbonaceous, in part primary, in part secondary, and of this material some is anthropogenic and some biogenic. While the heterogeneity of atmospheric aerosols complicates the problem of understanding their loading and distribution, it may well be the key to its solution. By detailed examination of the materials comprising aerosols it is possible to infer the sources of these materials. It may be possible as well to identify specific health impairing agents. The heterogeneity of aerosol particles is thus the key to identifying their sources, to understanding the processes that govern their loading and properties, and to devising control strategies that are both effective and efficient. Future research must therefore take cognizance of differences among aerosol particles and use these differences to advantage.
STORM in Monte Carlo reactor physics calculations KAUR TUTTELBERG
Haviland, David
STORM in Monte Carlo reactor physics calculations KAUR TUTTELBERG Master of Science Thesis Carlo reactor physics criticality calculations. This is achieved by optimising the number of neutron for more efficient Monte Carlo reactor physics calculations, giving results with errors that can
The melting lines of model systems calculated from coexistence simulations
Song, Xueyu
rapidly as a function of the potential cutoff, indicating that long-range corrections to the free energies of the solid and liquid phases very nearly cancel. This approach provides an alternative to traditional methods them. Tradition- ally, these calculations have been made using free energy calculations: by calculating
Langlie Test Method Program for use with the HP-41CV/X calculator
Kopczewski, M.R.
1987-10-01T23:59:59.000Z
Explosive component designers need to test the sensitivity of some unit response as a function level of stress, for example, the sensitivity of a detonator or ignitor bridgewire to input current. There exists a threshold level, above which the detonator will function and below which it will not. Statistical testing of explosive components often requires destructive testing of expensive hardware. If the unit functions, it is destroyed; and if it doesn't fire, the results from any further testing cannot be relied on because the initial test affects the detonator. In order to obtain meaningful results and not expend a large number of units, the Langlie ''One-Shot'' Method of testing is employed. Typical component attributes that require Langlie testing include ''all-fire'' and ''no-fire'' tests to determine threshold levels of performance. Generally, any sensitivity testing lends itself to the Langlie method. This method has also been shown to be insensitive to design. Typically, support test groups and venders implement the test method with their own computers. The method is subject to some interpretation which may lead to inconsistency in results from facility to facility. Another concern is that an error made in choosing a stimulus level will affect subsequent levels, resulting in an analysis that is not a true Langlie. A program has been written for the HP-41CV/X calculator in order to standardize the Langlie test procedures at the various facilities, and to minimize the possibilities of introducing errors in the test method. A distinct advantage of using the calculator is the ability to hand carry it in the field and perform the Langlie test method at remote locations. 2 refs.
Contributions of different neutron pairs in different approaches for neutrinoless double beta decay
Alberto Escuderos; Amand Faessler; Vadim Rodin; Fedor Simkovic
2010-06-07T23:59:59.000Z
The methods used till now to calculate the neutrinoless double beta decay matrix elements are: the Quasiparticle Random Phase Approximation (QRPA), the Shell Model (SM), the angular momentum projected Hartee-Fock-Bogoliubov approach (HFB) and the Interacting Boson Model (IBM). The different approaches are compared specifically concerning the the angular momenta and parities of the neutron pairs, which are changed into two protons by the $0\
Full Core, Heterogeneous, Time Dependent Neutron Transport Calculations with the 3D Code DeCART
Hursin, Mathieu
2010-01-01T23:59:59.000Z
for multi- dimensional reactor calculation." Atomkernenergiein Light Water Reactor calculations, which are processedlight water reactor diffusion calculations." Nuclear Science
CRC handbook of nuclear reactors calculations. Vol. III
Ronen, Y.
1986-01-01T23:59:59.000Z
This handbook breaks down the complex field of nuclear reactor calculations into major steps. Each step presents a detailed analysis of the problems to be solved, the parameters involved, and the elaborate computer programs developed to perform the calculations. This book bridges the gap between nuclear reactor theory and the implementation of that theory, including the problems to be encountered and the level of confidence that should be given to the methods described. Volume III: Control Rods and Burnable Absorber Calculations. Perturbation Theory for Nuclear Reactor Analysis. Thermal Reactors Calculations. Fast Reactor Calculations. Seed-Blanket Reactors. Index.
Well performance graph simplifies field calculations
De Ghetto, G.
1987-05-01T23:59:59.000Z
Graphic Methods are widely employed in order to understand overall well behavior using only surface parameters. The authors propose a new graphic method, used successfully by Agip for oil and gas wells in Italy, Libya, Nigeria and Tunisia. The well performance graph helps solve many production problems, including estimation of: inflow performance relationship; causes of rate decline throughout well life; and production rate and bottomhole flowing pressure for various pressures upstream of the surface choke, and vice-versa. This method differs from others by using flow behavior through the choke for both critical and subcritical conditions. Equations describing flow through the formation, string and surface choke are also used. Results are quite reliable when these theoretical equations are calibrated with field data, either from the well concerned or from nearby wells producing the same fluid. This article describes the technique as it applies to oil wells. The methodology for gas wells is similar.
Design calculations and measurements of a dipole magnet with Permendur pole pieces
Early, R.A.; Cobb, J.K.; Oijala, J.E.
1989-03-01T23:59:59.000Z
A redesign of the SLC South Linac-to-Ring beam line required that the width of a good field of three of the bending magnets be increased while utilizing the same yoke and coils. Further requirements were that the resulting magnets should have the same strength at two different operating currents as the original magnets. The idea of replacing the steel poles with pole pieces of the high permeability material Permendur was investigated. Design calculations were done using TOSCA and POISSON. An existing prototype magnet was modified with Permendur poles, and magnetic measurements were done. The new magnets were completed, and measurements agreed well with the calculations. 4 refs., 14 figs.
Radhakrishnan, Archana, E-mail: anju.archana@gmail.com [B.Tech, Engineering Physics, National Institute Of Technology, Calicut (India); Murugesan, Dr V., E-mail: murugesh@serc.iisc.in [Assistant Professor, Supercomputer Education and Research Centre, Indian Institute of Science, Bangalore (India)
2014-10-15T23:59:59.000Z
The electromagnetic theory of light explains the behavior of light in most of the domains quite accurately. The problem arises when the exact solution of the Maxwell's equation is not present, in case of objects with arbitrary geometry. To find the extinction cross-section and lifetime of the gold nanoparticle, the software FDTD solutions 8.6 by Lumerical is employed. The extinction cross-sections and lifetimes of Gold nanospheres of different sizes and arrangements are studied using pulse lengths of the order of femtoseconds. The decay constant and other properties are compared. Further, the lifetimes are calculated using frequency and time domain calculations.
Mapping motion from 4D-MRI to 3D-CT for use in 4D dose calculations: A technical feasibility study
Boye, Dirk [Center for Proton Therapy, Paul Scherrer Institut, 5232 Villigen-PSI (Switzerland); Computer Vision Laboratory, ETH Zuerich, 8092 Zuerich (Switzerland); Lomax, Tony [Center for Proton Therapy, Paul Scherrer Institut, 5232 Villigen-PSI (Switzerland); ETH Zuerich, 8092 Zuerich (Switzerland); Knopf, Antje [Center for Proton Therapy, Paul Scherrer Institut, 5232 Villigen-PSI (Switzerland)
2013-06-15T23:59:59.000Z
Purpose: Target sites affected by organ motion require a time resolved (4D) dose calculation. Typical 4D dose calculations use 4D-CT as a basis. Unfortunately, 4D-CT images have the disadvantage of being a 'snap-shot' of the motion during acquisition and of assuming regularity of breathing. In addition, 4D-CT acquisitions involve a substantial additional dose burden to the patient making many, repeated 4D-CT acquisitions undesirable. Here the authors test the feasibility of an alternative approach to generate patient specific 4D-CT data sets. Methods: In this approach motion information is extracted from 4D-MRI. Simulated 4D-CT data sets [which the authors call 4D-CT(MRI)] are created by warping extracted deformation fields to a static 3D-CT data set. The employment of 4D-MRI sequences for this has the advantage that no assumptions on breathing regularity are made, irregularities in breathing can be studied and, if necessary, many repeat imaging studies (and consequently simulated 4D-CT data sets) can be performed on patients and/or volunteers. The accuracy of 4D-CT(MRI)s has been validated by 4D proton dose calculations. Our 4D dose algorithm takes into account displacements as well as deformations on the originating 4D-CT/4D-CT(MRI) by calculating the dose of each pencil beam based on an individual time stamp of when that pencil beam is applied. According to corresponding displacement and density-variation-maps the position and the water equivalent range of the dose grid points is adjusted at each time instance. Results: 4D dose distributions, using 4D-CT(MRI) data sets as input were compared to results based on a reference conventional 4D-CT data set capturing similar motion characteristics. Almost identical 4D dose distributions could be achieved, even though scanned proton beams are very sensitive to small differences in the patient geometry. In addition, 4D dose calculations have been performed on the same patient, but using 4D-CT(MRI) data sets based on variable breathing patterns to show the effect of possible irregular breathing on active scanned proton therapy. Using a 4D-CT(MRI), including motion irregularities, resulted in significantly different proton dose distributions. Conclusions: The authors have demonstrated that motion information from 4D-MRI can be used to generate realistic 4D-CT data sets on the basis of a single static 3D-CT data set. 4D-CT(MRI) presents a novel approach to test the robustness of treatment plans in the circumstance of patient motion.
Calculating Energy Savings in High Performance Residential Buildings Programs: Preprint
Hendron, B.; Rarrar-Nagy, S.; Anderson, R.; Judkoff, R.; Reeves, P.; Hancock, E.
2003-08-01T23:59:59.000Z
Accurate and meaningful energy savings calculations are essential for the evaluation of residential energy efficiency programs sponsored by the U.S. Department of Energy (DOE), such as the Building America Program (a public-private partnership designed to achieve significant energy savings in the residential building sector). The authors investigated the feasibility of applying existing performance analysis methodologies such as the Home Energy Rating System (HERS) and the International Energy Conservation Code (IECC) to the high performance houses constructed under Building America, which sometimes achieve whole-house energy savings in the 50-70% range. However, because Building America addresses all major end-use loads and because the technologies applied to Building America houses often exceed what is envisioned by energy codes and home-rating programs, the methodologies used in HERS and IECC have limited suitability, and a different approach was needed. The authors have researched these issues extensively over the past several years and developed a set of guidelines that draws upon work done by DOE's Energy Information Administration, the California Energy Commission, the International Code Council, RESNET, and other organizations that have developed similar methodologies to meet their needs. However, the final guidelines are tailored to provide accurate techniques for quantifying energy savings achieved by Building America to help policymakers assess the effectiveness of the program.
Yi-Ping Qin
2004-11-13T23:59:59.000Z
In this paper, we employ the peak count rate{\\bf \\}$C_p$ and the total count $C_{total}$ of light curves to study in the corresponding aspects the relationship between different channel light curves. To make a direct comparison between count rates of different channel light curves we introduce a plot of $C(\\tau)$ versus $C_H(\\tau)$, where $C(\\tau)$ is the count rate of a channel and $C_H(\\tau)$ is the count rate of a definite cannel, channel H (see the text). According to the plot we define $\\Delta C_{\\max}$ as the maximum deviation of the two count rate values of $C(\\tau)$ associated with a same count rate value of $% C_H(\\tau)$ and define $\\Delta S$ as the area confined by the close curve of $C(\\tau)$ in the plot to measure the difference of the rising and decaying portions of a light curve relative to the count rate of channel H. Under the assumption that some GRBs observed are in the stage of fireballs which expand relativistically, predictions on the relationships between the four quantities{\\bf (}$C_p$, $C_{total}$, $\\Delta C_{\\max}$, and $\\Delta S$) and energy within a wide band, calculated with different rest frame radiation forms and two typical Lorentz factors ($\\Gamma =20$ and 200), are made and presented, which would make the test of our model with the coming Swift data easier. Interpretations to the relationships within the mechanism of fireballs are also presented.
Quantum Monte Carlo calculation of the equation of state of neutron matter
Gandolfi, S.; Illarionov, A. Yu.; Schmidt, K. E.; Pederiva, F.; Fantoni, S. [International School for Advanced Studies, SISSA Via Beirut 2/4 I-34014 Trieste (Italy) and INFN, Sezione di Trieste, Trieste (Italy); Department of Physics, Arizona State University, Tempe, Arizona 85287 (United States); Dipartimento di Fisica dell'Universita di Trento, via Sommarive 14, I-38050 Povo, Trento (Italy) and INFN, Gruppo Collegato di Trento, Trento (Italy); International School for Advanced Studies, SISSA Via Beirut 2/4 I-34014 Trieste (Italy); INFN, Sezione di Trieste, Trieste, Italy and INFM DEMOCRITOS National Simulation Center, Via Beirut 2/4 I-34014 Trieste (Italy)
2009-05-15T23:59:59.000Z
We calculated the equation of state of neutron matter at zero temperature by means of the auxiliary field diffusion Monte Carlo (AFDMC) method combined with a fixed-phase approximation. The calculation of the energy was carried out by simulating up to 114 neutrons in a periodic box. Special attention was given to reducing finite-size effects at the energy evaluation by adding to the interaction the effect due to the truncation of the simulation box, and by performing several simulations using different numbers of neutrons. The finite-size effects due to kinetic energy were also checked by employing the twist-averaged boundary conditions. We considered a realistic nuclear Hamiltonian containing modern two- and three-body interactions of the Argonne and Urbana family. The equation of state can be used to compare and calibrate other many-body calculations and to predict properties of neutron stars.
Calculation of sensitivity coefficients for a neutron well logging tool
Chen, Chien-Hsiang
1993-01-01T23:59:59.000Z
OF SCIENCE August 1993 Major Subject: Nuclear Engineering CALCULATION OF SENSITIVITY COEFFICIENTS FOR A NEUTRON WELL LOGGING TOOL A Thesis by CHIEN-HSIANG CHEN Approved as to style and content by: Theodore A. Parish (Chair of Committee) Ron R. Hart... to calculate sensitivity coefficients. A benchmark problem for a neutron porosity logging tool was set up to test the methodology mentioned above. Through several tests and calculations of sensitivity coefficients, it was found that the response...
A Cosmology Calculator for the World Wide Web
Edward L. Wright
2006-10-10T23:59:59.000Z
A cosmology calculator that computes times and distances as a function of redshift for user-defined cosmological parameters is available on the World Wide Web. This note gives the formulae used by the cosmology calculator and discusses some of its implementation. A version of the calculator that allows one to specify the equation of state parameter w and w' and neutrino masses, and a version for converting the light travel times usually given in the popular press into redshifts are also available.
Calculation of the compressibility factor and thermodynamic properties for methane
Dowling, Dennis William
1966-01-01T23:59:59.000Z
of Saturated Vapor Volumes Reported by Bloomer and Parent (5) and Those Calculated in This Work Thermodynamic Properties Calculated by Use of Berlin Equation Thermodynamic Properties Calculated by Use of Benedict-Webb-Rubin Equation 35 36 39 40 48..., and Smith (15), Gardoso (7), and Bloomer and Parent (5) have reported experimental vapor pressure data and values for the saturated liquid density. Cardoso (7) and Bloomer and Parent (5) have also reported values for saturated vapor densities. A critical...
Calculation of tunneling rates across a barrier with continuous potential
Sina Khorasani
2011-04-10T23:59:59.000Z
Here, approximate, but accurate expressions for calculation of wavefunctions and tunneling rates are obtained using the method of uniform asymptotic expansion.
First Principles Calculations and NMR Spectroscopy of Electrode...
Broader source: Energy.gov (indexed) [DOE]
First Principles Calculations and NMR Spectroscopy of Electrode Materials G. Ceder Massachusetts Institute of technology and C. P Grey Cambridge University and Stony Brook...
Energy Cost Savings Calculator for Commercial Boilers: Closed...
Office of Environmental Management (EM)
Commercial Boilers: Closed Loop, Space Heating Applications Only Energy Cost Savings Calculator for Commercial Boilers: Closed Loop, Space Heating Applications Only This cost...
Cascade calculation of subthreshold. pi. sup 0 production
Gavron, A.; Yariv, Y. (Physics Division, Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (US))
1990-05-01T23:59:59.000Z
Intranuclear cascade calculations are found to provide a good description of the various features of subthreshold {pi}{sup 0} production in nucleon-nucleus collisions.
Formation enthalpies by mixing GGA and GGA + U calculations
Jain, Anubhav
Standard approximations to the density functional theory exchange-correlation functional have been extraordinary successful, but calculating formation enthalpies of reactions involving compounds with both localized and ...
Examen de calcul matriciel Licence MASHS -MI -SPC, semestre 2
Lafont, Yves
Examen de calcul matriciel Licence MASHS - MI - SPC, semestre 2 14 juin 2007 DurÃ©e de l'Ã©preuve : 3
assessment calculations related: Topics by E-print Network
Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)
chi values surrounding the common rotameric states of leucine and valine. Relative free enegy slices were calculated from the biased trajectories using the weighted histogram...
First Principles Calculations and NMR Spectroscopy of Electrode...
Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site
Calculations and NMR Spectroscopy of Electrode Materials 2011 DOE Hydrogen and Fuel Cells Program, and Vehicle Technologies Program Annual Merit Review and Peer Evaluation...
A High-Performance Fortran Code to Calculate Spin- and Parity-Dependent Nuclear Level Densities
R. Sen'kov; M. Horoi; V. G. Zelevinsky
2012-06-20T23:59:59.000Z
A high-performance Fortran code is developed to calculate the spin- and parity-dependent shell model nuclear level densities.The algorithm is based on the extension of methods of statistical spectroscopy and implies exact calculation of the first and second Hamiltonian moments for different configurations at fixed spin and parity. The proton-neutron formalism is used. We have applied the method for calculating the level densities for a set of nuclei in the sd-, pf-, and pf+g9/2 - model spaces. Examples of the calculations for 28Si (in the sd-model space) and 64Ge (in the pf+g9/2-model space) are presented. To illustrate the power of the method we estimate the ground state energy of 64Ge in the larger model space pf+g9/2, which is not accessible to direct shell model diagonalization due to the prohibitively large dimension, by comparing with the nuclear level densities at low excitation energy calculated in the smaller model space pf.
A High-Performance Fortran Code to Calculate Spin- and Parity-Dependent Nuclear Level Densities
Sen'kov, R; Zelevinsky, V G
2012-01-01T23:59:59.000Z
A high-performance Fortran code is developed to calculate the spin- and parity-dependent shell model nuclear level densities.The algorithm is based on the extension of methods of statistical spectroscopy and implies exact calculation of the first and second Hamiltonian moments for different configurations at fixed spin and parity. The proton-neutron formalism is used. We have applied the method for calculating the level densities for a set of nuclei in the sd-, pf-, and pf+g9/2 - model spaces. Examples of the calculations for 28Si (in the sd-model space) and 64Ge (in the pf+g9/2-model space) are presented. To illustrate the power of the method we estimate the ground state energy of 64Ge in the larger model space pf+g9/2, which is not accessible to direct shell model diagonalization due to the prohibitively large dimension, by comparing with the nuclear level densities at low excitation energy calculated in the smaller model space pf.
CALCULATION OF THE NEUTRON NOISE INDUCED BY SHELL-MODE
DemaziÃ¨re, Christophe
CALCULATION OF THE NEUTRON NOISE INDUCED BY SHELL-MODE FISSION REACTORS CORE-BARREL VIBRATIONS-REGION SLAB REACTOR MODEL CARL SUNDE,* CHRISTOPHE DEMAZIÃ?RE, and IMRE PÃZSIT Chalmers University of Technology for Publication October 12, 2005 The subject of this paper is the calculation of the in-core neutron noise induced
Overview of `classical' or `standardized' DPA calculation stemming from the
McDonald, Kirk
Overview of `classical' or `standardized' DPA calculation stemming from the reactor world. Colin English, NNL 7 April 2014 #12;2 Purpose Â· Overview of `classical' or `standardized' DPA calculation stemming from the reactor world. Â· Current Status Â· Details of accepted Methodology Â· Known Limitations
Calculating reactor transfer functions by Pade approximation via Lanczos algorithm
PÃ¡zsit, Imre
Calculating reactor transfer functions by PadeÃ? approximation via Lanczos algorithm Zhifeng Kuang a function of a reactor, i.e. the neutron noise induced by a localised perturbation is calculated in one, *,1 , Imre PaÃ? zsit a , Axel Ruhe b a Department of Reactor Physics, Chalmers University of Technology
Independent review of SCDAP/RELAP5 natural circulation calculations
Martinez, G.M.; Gross, R.J.; Martinez, M.J.; Rightley, G.S.
1994-01-01T23:59:59.000Z
A review and assessment of the uncertainties in the calculated response of reactor coolant system natural circulation using the SCDAP/RELAP5 computer code were completed. The SCDAP/RELAP5 calculation modeled a station blackout transient in the Surry nuclear power plant and concluded that primary system depressurization from natural circulation induced primary system failure is more likely than previously thought.
General calculations using graphics hardware, with application to interactive caustics
Paris-Sud XI, UniversitÃ© de
General calculations using graphics hardware, with application to interactive caustics Chris Trendall and A. James Stewart iMAGISÂGRAVIR/IMAG and University of Toronto Abstract. Graphics hardware has general computation. This paper shows that graphics hardware can perform general calculations, which
Model calculations of nuclear data for biologically-important elements
Chadwick, M.B.; Blann, M.; Reffo, G. [Lawrence Livermore National Lab., CA (United States); Young, P.G. [Los Alamos National Lab., NM (United States)
1994-05-01T23:59:59.000Z
We describe calculations of neutron-induced reactions on carbon and oxygen for incident energies up to 70 MeV, the relevant clinical energy in radiation neutron therapy. Our calculations using the FKK-GNASH, GNASH, and ALICE codes are compared with experimental measurements, and their usefulness for modeling reactions on biologically-important elements is assessed.
Computing Partial Eigenvalue Sum in Electronic Structure Calculations
Bai, Zhaojun
and CPU time. In the application of electronic structure calculations in molecular dynamics, the newComputing Partial Eigenvalue Sum in Electronic Structure Calculations Z. Bai M. Faheyy G. Golubz M where computation of the total energy of an electronic structure requires the evaluation of partial
Dynamic Algorithm Selection in Parallel GAMESS Calculations Nurzhan Ustemirov
Sosonkina, Masha
and Molecular Electronic Structure System (GAMESS) used for ab initio molecular quantum chemistry calculationsDynamic Algorithm Selection in Parallel GAMESS Calculations Nurzhan Ustemirov Masha Sosonkina, network, or disk I/O. For large-scale scientific applications, dynamic adjustments to a computationally
IMPROVEMENTS TO THE RADIANT TIME SERIES METHOD COOLING LOAD CALCULATION
IMPROVEMENTS TO THE RADIANT TIME SERIES METHOD COOLING LOAD CALCULATION PROCEDURE By BEREKET, Australia 1998 Submitted to the Faculty of the Graduate College of the Oklahoma State University in partial TO THE RADIANT TIME SERIES METHOD COOLING LOAD CALCULATION PROCEDURE Dissertation Approved: Dr. Jeffrey D
RETI Resource Valuation Methodology Cost of Generation Calculator
) Â· Cost of equity investment in capital Â· Cost of financing capital Â· Taxes, including investmentRETI Resource Valuation Methodology Cost of Generation Calculator The Cost of Generation Calculator determines the levelized cost of generating power over the life of the resource, and is an input
Processus communicants Communication synchrone CSP/CCS/-calcul
Grigoras, .Romulus
Processus communicants Communication synchrone CSP/CCS/-calcul Rendez-vous étendu Ada Huitième partie Processus communicants CSP/Ada Systèmes concurrents 2 / 44 #12;Processus communicants Communication synchrone CSP/CCS/-calcul Rendez-vous étendu Ada Principes Synchronisation Désignation
Semi-empirical calculation of quenching factors for scintillators: new results
Tretyak, V I
2014-01-01T23:59:59.000Z
New results of calculation of quenching factors for ions in scintillators in semi-empirical approach described in [V.I. Tretyak, Astropart. Phys. 33 (2010) 40] are presented. In particular, they give additional arguments in favour of hypothesis that quenching factors for different particles can be described with the same Birks factor kB, if all the data were collected in the same conditions and processed in the same way.
Ellis, Ronald J.; Yugo, James J.; Frankle, S. C. (Stephanie C.); Little, R. C. (Robert C.)
2003-01-01T23:59:59.000Z
A project was undertaken to assess the MENDF5 and MENDF6 nuclear data libraries through the analysis of 86 critical assembly benchmarks using the LANL discrete ordinates transport code PARTISN. As an initial analysis of the effects of some limitations in the MENDF libraries, this current work assesses differences in k,,a calculations between the PARTISN cases (with MENDF5 and MENDF6 nuclear data libraries) and MCNP cases, and compares these results to the experimental data.
Lattice calculation of the pion form factor with Ginsparg-Wilson-type fermions
Capitani, Stefano; Gattringer, Christof; Lang, C.B. [Institut fuer Physik, FB Theoretische Physik, Universitaet Graz, A-8010 Graz (Austria)
2006-02-01T23:59:59.000Z
Results for Monte Carlo calculations of the electromagnetic vector and scalar form factors of the pion in a quenched simulation are presented. We work with two different lattice volumes up to a spatial size of 2.4 fm at a lattice spacing of 0.148 fm. The pion form factors in the spacelike region are determined for pion masses down to 340 MeV.
A lattice calculation of the pion form factor with Ginsparg-Wilson-type fermions
Stefano Capitani; Christof Gattringer; C. B. Lang
2006-02-03T23:59:59.000Z
Results for Monte Carlo calculations of the electromagnetic vector and scalar form factors of the pion in a quenched simulation are presented. We work with two different lattice volumes up to a spatial size of 2.4 fm at a lattice spacing of 0.148 fm. The pion form factors in the space-like region are determined for pion masses down to 340 MeV.
Use of Carbon Mesh Anodes and the Effect of Different Pretreatment
Use of Carbon Mesh Anodes and the Effect of Different Pretreatment Methods on Power Production, China, and Department of Civil and Environmental Engineering, Penn State University, 231Q Sackett electrode spacing improves power generation. Carbon cloth and carbon paper materials typically used
Water-thinnable polymers for durable coatings for different materials
Jankowski, Piotr, E-mail: piotr.jankowski@ichp.pl; Kijowska, Dorota, E-mail: piotr.jankowski@ichp.pl [Industrial Chemistry Research Institute, Department of Polyesters, Epoxides and Polyurethanes, 8 Rydygiera Str., 01-793 Warszawa (Poland)
2014-05-15T23:59:59.000Z
The methods of obtaining water-thinnable polymers - water-thinnable unsaturated polyester resins (WTUPR) - by polycondensation were elaborate and optimized. As hydrophilic monomers different types of sulfonate monomers were used. The monomers, with sulfonate groups and other reactive groups, were obtained by sulfonation of organic compounds with satisfactory yield. All products were analyzed by {sup 1}H NMR and {sup 13}C NMR spectra. WTUPR were used as polymeric binders for coatings applications. Coatings with relatively high pendulum hardness, good properties and durability, useful for practical applications, were obtained. Typical existing equipment for the production of unsaturated polyester resins can be applied for the industrial preparation of WTUPR.
Calculation of Heating Values for the High Flux Isotope Reactor
Peterson, Joshua L [ORNL] [ORNL; Ilas, Germina [ORNL] [ORNL
2012-01-01T23:59:59.000Z
Calculating the amount of energy released by a fission reaction (fission Q value) and the heating rate distribution in a nuclear reactor is an important part of the safety analysis. However, these calculations can become very complex. One of the codes that can be used for this type of analyses is the Monte Carlo transport code MCNP5. Currently it is impossible to calculate the Q value and heating rate disposition for delayed beta and delayed gamma particles directly from MCNP5. The purpose of this paper is to outline a rigorous method for indirectly calculating the Q values and heating rates in the High Flux Isotope Reactor (HFIR), based on previous similar studies carried out for very high-temperature reactor configurations. This method has been applied in this study to calculate heating rates for the beginning of cycle (BOC) and end-of-cycle (EOC) states of HFIR. In addition, the BOC results obtained for HFIR are compared with corresponding results for the Advanced Test Reactor. The fission Q value for HFIR was calculated as 200.2 MeV for the BOC and 201.3 MeV for the EOC. It was also determined that 95.1% and 95.4% of the heat was deposited within the HFIR fuel plates for the BOC and EOC models, respectively. This methodology can also be used for heating rate calculations for HFIR experiments.
IN-DRIFT MICROBIAL COMMUNITIES MODEL VALIDATION CALCULATIONS
D.M. Jolley
2001-12-18T23:59:59.000Z
The objective and scope of this calculation is to create the appropriate parameter input for MING 1.0 (CSCI 30018 V1.0, CRWMS M&O 1998b) that will allow the testing of the results from the MING software code with both scientific measurements of microbial populations at the site and laboratory and with natural analogs to the site. This set of calculations provides results that will be used in model validation for the ''In-Drift Microbial Communities'' model (CRWMS M&O 2000) which is part of the Engineered Barrier System Department (EBS) process modeling effort that eventually will feed future Total System Performance Assessment (TSPA) models. This calculation is being produced to replace MING model validation output that is effected by the supersession of DTN M09909SPAMINGl.003 using its replacement DTN M00106SPAIDMO 1.034 so that the calculations currently found in the ''In-Drift Microbial Communities'' AMR (CRWMS M&O 2000) will be brought up to date. This set of calculations replaces the calculations contained in sections 6.7.2, 6.7.3 and Attachment I of CRWMS M&O (2000) As all of these calculations are created explicitly for model validation, the data qualification status of all inputs can be considered corroborative in accordance with AP-3.15Q. This work activity has been evaluated in accordance with the AP-2.21 procedure, ''Quality Determinations and Planning for Scientific, Engineering, and Regulatory Compliance Activities'', and is subject to QA controls (BSC 2001). The calculation is developed in accordance with the AP-3.12 procedure, Calculations, and prepared in accordance with the ''Technical Work Plan For EBS Department Modeling FY 01 Work Activities'' (BSC 200 1) which includes controls for the management of electronic data.
CRC handbook of nuclear reactors calculations. Vol. II
Ronen, Y.
1986-01-01T23:59:59.000Z
This handbook breaks down the complex field of nuclear reactor calculations into major steps. Each step presents a detailed analysis of the problems to be solved, the parameters involved, and the elaborate computer programs developed to perform the calculations. This book bridges the gap between nuclear reactor theory and the implementation of that theory, including the problems to be encountered and the level of confidence that should be given to the methods described. Volume II: Monte Carlo Calculations for Nuclear Reactors. In-Core Management of Four Reactor Types. In-Core Management in CANDU-PHW Reactors. Reactor Dynamics. The Theory of Neutron Leakage in Reactor Lattices. Index.
Practical calculation of amplitudes for electron-impact ionization
McCurdy, C. William; Horner, Daniel A.; Rescigno, Thomas N.
2001-02-01T23:59:59.000Z
An integral expression that is formally valid only for short-range potentials is applied to the problem of calculating the amplitude for electron-impact ionization. It is found that this expression provides a practical and accurate path to the calculation of singly differential cross sections for electron-impact ionization. Calculations are presented for the Temkin-Poet and collinear models for ionization of hydrogen by electron impact. An extension of the finite-element approach using the discrete-variable representation, appropriate for potentials with discontinuous derivatives like the Temkin-Poet interaction, is also presented.
Relativistic mean field calculations in neutron-rich nuclei
Gangopadhyay, G.; Bhattacharya, Madhubrata [Department of Physics, University of Calcutta, 92 Acharya Prafulla Chandra Road, Kolkata 700 009 (India); Roy, Subinit [Saha Institute of Nuclear Physics, Block AF, Sector 1, Kolkata- 700 064 (India)
2014-08-14T23:59:59.000Z
Relativistic mean field calculations have been employed to study neutron rich nuclei. The Lagrange's equations have been solved in the co-ordinate space. The effect of the continuum has been effectively taken into account through the method of resonant continuum. It is found that BCS approximation performs as well as a more involved Relativistic Continuum Hartree Bogoliubov approach. Calculations reveal the possibility of modification of magic numbers in neutron rich nuclei. Calculation for low energy proton scattering cross sections shows that the present approach reproduces the density in very light neutron rich nuclei.
First-principles Calculation of Excited State Spectra in QCD
Dudek, Jozef J. [Jefferson Laboratory, 12000 Jefferson Avenue Suite 1, Newport News, VA 23606 (United States); Department of Physics, Old Dominion University, Norfolk, VA 23529 (United States); Edwards, Robert G.; Richards, David G.; Thomas, Christopher E. [Jefferson Laboratory, 12000 Jefferson Avenue Suite 1, Newport News, VA 23606 (United States); Peardon, Michael J. [School of Mathematics, Trinity College, Dublin 2 (Ireland)
2011-05-24T23:59:59.000Z
Recent progress at understanding the excited state spectra of mesons and baryons is described. I begin by outlining the application of the variational method to compute the spectrum of QCD, and then present results for the excited meson spectrum, with continuum quantum numbers of the states clearly delineated. I emphasise the need to extend the calculation to encompass multi-hadron contributions, and describe a recent calculation of the I = 2{pi}{pi} energy-dependent phase shifts as a precursor to the study of channels with resonant behavior. I conclude with recent results for the low lying baryon spectrum, and the prospects for future calculations.
DemaziÃ¨re, Christophe
Comparative study of 2-group P1 and diffusion theories for the calculation of the neutron noise of the neutron flux around its mean value, is calculated in 2-group P1 and diffusion theories for a 2-region slab reactor using Green's function technique. The applicability of diffusion theory for different types
Goddard III, William A.
Calculation of Solvation Free Energies of Charged Solutes Using Mixed Cluster/Continuum Models methodologies make systematic errors in the computed free energies because of the incorrect accounting consideration. We analyze two different thermodynamic cycles for calculating the solvation free energies
The Use of Graphics Calculator in a Matriculation Statistics Classroom: A Malaysian Perspective
Krishnan, Saras; Idris, Noraini
2013-01-01T23:59:59.000Z
mathematics: Why graphics calculator? Proceedings of the 2Learning statistics with graphics calculator: A case study.Learning statistics with graphics calculator: Students’
Calculating the hyperWiener index of benzenoid hydrocarbons
Klavzar, Sandi
Calculating the hyperÂWiener index of benzenoid hydrocarbons Petra Zigert1 , Sandi Klavzar1) is not easy, especially in the case of large polycyclic molecules, such as benzenoid hydrocarbons. Some time
Calculating the hyper--Wiener index of benzenoid hydrocarbons
Klavzar, Sandi
Calculating the hyper--Wiener index of benzenoid hydrocarbons Petra Å¸ Zigert 1 , Sandi KlavÅ¸ zar 1. (1) is not easy, especially in the case of large polycyclic molecules, such as benzenoid hydrocarbons
Reactor physics calculation of BWR fuel bundles containing gadolinia
Morales, Diego
1977-01-01T23:59:59.000Z
A technique for the calculation of the neutronic behavior of BWR fuel bundles has been developed and applied to a Vermont Yankee fuel bundle. The technique is based on a diffusion theory treatment of the bundle, with ...
Universal calculation formula and calibration method in Fourier transform profilometry
Wen Yongfu; Li Sikun; Cheng Haobo; Su Xianyu; Zhang Qican
2010-12-01T23:59:59.000Z
We propose a universal calculation formula of Fourier transform profilometry and give a strict theoretical analysis about the phase-height mapping relation. As the request on the experimental setup of the universal calculation formula is unconfined, the projector and the camera can be located arbitrarily to get better fringe information, which makes the operation flexible. The phase-height calibration method under the universal condition is proposed, which can avoid measuring the system parameters directly. It makes the system easy to manipulate and improves the measurement velocity. A computer simulation and experiment are conducted to verify its validity. The calculation formula and calibration method have been applied to measure an object of 22.00 mm maximal height. The relative error of the measurement result is only 0.59%. The experimental results prove that the three-dimensional shape of tested objects can be reconstructed exactly by using the calculation formula and calibration method, and the system has better universality.
CRAC calculations for accident sections of environmental statements
Johnson, J.D.; Ritchie, L.T.
1983-03-01T23:59:59.000Z
The CRAC2 computer code was adapted to the calculation requirements of Draft/Final Environmental Impact Statement (DES/FES) casework analysis for the Nuclear Regulatory Commission. CRAC is a revised version of the CRAC (Calculation of Reactor Accident Consequences) computer code developed in support of the Reactor Safety Study, WASH-1400. A graphical output package was developed for displaying CRAC2 computed results. All phases of the casework analysis calculations from initial data formatting to plotting of calculated results are executed through the use of procedure files on the Idaho National Engineering Laboratory (INEL) computing system at Idaho Falls, Idaho. The INEL computing system operates under the Control Data Corporation (CDC) NOS/BE Operating System (Level 518) and Intercom Version 5.
Calculation of Accurate Hexagonal Discontinuity Factors for PARCS
Pounders. J., Bandini, B. R. , Xu, Y, and Downar, T. J.
2007-11-01T23:59:59.000Z
In this study we derive a methodology for calculating discontinuity factors consistent with the Triangle-based Polynomial Expansion Nodal (TPEN) method implemented in PARCS for hexagonal reactor geometries. The accuracy of coarse-mesh nodal methods is greatly enhanced by permitting flux discontinuities at node boundaries, but the practice of calculating discontinuity factors from infinite-medium (zero-current) single bundle calculations may not be sufficiently accurate for more challenging problems in which there is a large amount of internodal neutron streaming. The authors therefore derive a TPEN-based method for calculating discontinuity factors that are exact with respect to generalized equivalence theory. The method is validated by reproducing the reference solution for a small hexagonal core.
Calculating Horsepower Requirements and Sizing Supply Pipelines for Irrigation
Fipps, Guy
1995-09-05T23:59:59.000Z
Pumping costs are often one of the largest single expenses in irrigated agriculture. This publication explains how to lower pumping costs by calculating horsepower requirements and sizing supply pipelines correctly. Examples take the reader through...
Protein Thermostability Calculations Using Alchemical Free Energy Simulations
de Groot, Bert
Protein Thermostability Calculations Using Alchemical Free Energy Simulations Daniel Seeliger by alterations in the free energy of folding. Growing computational power, however, increasingly allows us to use alchem- ical free energy simulations, such as free energy perturbation or thermodynamic integration
Is Ring breaking feasible in relative binding free energy calculations?
Liu, S; Wang, L; Mobley, DL
2015-01-01T23:59:59.000Z
Essex, J. W. Rigorous Free Energy Calculations in Structure-of Hydration Free Energies for SAMPL. J. Comput. -Aided Mol.Basic Ingredients of Free Energy Calcula- tions: A Review.
A computer program for HVDC converter station RF noise calculations
Kasten, D.G.; Caldecott, R.; Sebo, S.A. (Ohio State Univ., Columbus, OH (United States). Dept. of Electrical Engineering); Liu, Y. (Virginia Polytechnic Inst. State Univ., Blacksburg, VA (United States). Bradley Dept. of Electrical Engineering)
1994-04-01T23:59:59.000Z
HVDC converter station operations generate radio frequency (RF) electromagnetic (EM) noise which could interfere with adjacent communication and computer equipment, and carrier system operations. A generic Radio Frequency Computer Analysis Program (RAFCAP) for calculating the EM noise generated by valve ignition of a converter station has been developed as part of a larger project. The program calculates RF voltages, currents, complex power, ground level electric field strength and magnetic flux density in and around an HVDC converter station. The program requires the converter station network to be represented by frequency dependent impedance functions. Comparisons of calculated and measured values are given for an actual HVDC station to illustrate the validity of the program. RAFCAP is designed to be used by engineers for the purpose of calculating the RF noise produced by the igniting of HVDC converter valves.
Automating journey fare calculation for transport for London
Maciejewski, Joshua J. (Joshua John)
2008-01-01T23:59:59.000Z
This thesis develops a method to automate journey fare calculation for Transport for London. Today, fares for every possible origin-destination station pair within the London Underground are prepared manually based on the ...
Process and Intermediate Calculations User AccessInputs Outputs
Process and Intermediate Calculations User AccessInputs Outputs Fire Behavior & Probability STARFire System Flow Valuation Processing Temporal Schedules Smoke · Zones · Zone impact · Emissions Fire and compare Valuation (Structured Elicit Process) 1) Value Layers: · Point (housing, cultural trees, etc
Kevin Christiansen "This week I got started on different project than I've
Zanibbi, Richard
solar panels from broken calculator panels), and other projects relating on different project than I've been working on in previous weeks. I began." Zach Kruchoski "This week I organized and typed up a paper regarding running
CRC handbook of nuclear reactors calculations. Vol. I
Ronen, Y.
1986-01-01T23:59:59.000Z
This handbook breaks down the complex field of nuclear reactor calculations into major steps. Each step presents a detailed analysis of the problems to be solved, the parameters involved, and the elaborate computer programs developed to perform the calculations. This book bridges the gap between nuclear reactor theory and the implementation of that theory, including the problems to be encountered and the level of confidence that should be given to the methods described.
Improved load models for multi-area reliability calculations
Pathak, Sanjesh
1992-01-01T23:59:59.000Z
IMPROVED LOAD MODELS FOR MULTI-AREA RELIABILITY CALCULATIONS A Thesis by SANJESH PATHAK Submitted to the Office of Graduate Studies of Texas ARM University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE May... 1992 Major Subject: Electrical Engineering IMPROVED LOAD MODELS FOR MULTI-AREA RELIABILITY CALCULATIONS A Thesis by SAN JESH PATHAK Approved as to style and content by: Chanan Singh (Chair of Committee) Prasad Enjeti (Member) Ces . Mal, e...
Scoping calculations of power sources for nuclear electric propulsion
Difilippo, F.C. [Oak Ridge National Lab., TN (United States)] [Oak Ridge National Lab., TN (United States)
1994-05-01T23:59:59.000Z
This technical memorandum describes models and calculational procedures to fully characterize the nuclear island of power sources for nuclear electric propulsion. Two computer codes were written: one for the gas-cooled NERVA derivative reactor and the other for liquid metal-cooled fuel pin reactors. These codes are going to be interfaced by NASA with the balance of plant in order to making scoping calculations for mission analysis.
Strategy Guideline: Accurate Heating and Cooling Load Calculations
Burdick, A.
2011-06-01T23:59:59.000Z
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.
Reservoir rock-property calculations from thin section measurements
Sneed, David Richard
1988-01-01T23:59:59.000Z
RESERVOIR ROCK-PROPERTY CALCULATIONS FROM THIN SECTION MEASUREMENTS A Thesis by DAVID RICHARD SNEED Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER... OF SCIENCE August 1988 Major Subject: Geology RESERVOIR ROCK-PROPERTY CALCULATIONS FROM THIN SECTION MEASUREMENTS A Thesis by DAVID RICHARD SNEED Approved as to style and content by: Robert R. Berg (Chair of Committee) ~ c(. Thomas T. Tieh (Member...
Smith, L.A.; Gallmeier, F.X. [Oak Ridge Institute for Science and Energy, TN (United States); Gehin, J.C. [Oak Ridge National Lab., TN (United States)] [and others
1995-05-01T23:59:59.000Z
The FOEHN critical experiment was analyzed to validate the use of multigroup cross sections and Oak Ridge National Laboratory neutronics computer codes in the design of the Advanced Neutron Source. The ANSL-V 99-group master cross section library was used for all the calculations. Three different critical configurations were evaluated using the multigroup KENO Monte Carlo transport code, the multigroup DORT discrete ordinates transport code, and the multigroup diffusion theory code VENTURE. The simple configuration consists of only the fuel and control elements with the heavy water reflector. The intermediate configuration includes boron endplates at the upper and lower edges of the fuel element. The complex configuration includes both the boron endplates and components in the reflector. Cross sections were processed using modules from the AMPX system. Both 99-group and 20-group cross sections were created and used in two-dimensional models of the FOEHN experiment. KENO calculations were performed using both 99-group and 20-group cross sections. The DORT and VENTURE calculations were performed using 20-group cross sections. Because the simple and intermediate configurations are azimuthally symmetric, these configurations can be explicitly modeled in R-Z geometry. Since the reflector components cannot be modeled explicitly using the current versions of these codes, three reflector component homogenization schemes were developed and evaluated for the complex configuration. Power density distributions were calculated with KENO using 99-group cross sections and with DORT and VENTURE using 20-group cross sections. The average differences between the measured values and the values calculated with the different computer codes range from 2.45 to 5.74%. The maximum differences between the measured and calculated thermal flux values for the simple and intermediate configurations are {approx} 13%, while the average differences are < 8%.
Rocklin, Gabriel J. [Department of Pharmaceutical Chemistry, University of California San Francisco, 1700 4th St., San Francisco, California 94143-2550, USA and Biophysics Graduate Program, University of California San Francisco, 1700 4th St., San Francisco, California 94143-2550 (United States)] [Department of Pharmaceutical Chemistry, University of California San Francisco, 1700 4th St., San Francisco, California 94143-2550, USA and Biophysics Graduate Program, University of California San Francisco, 1700 4th St., San Francisco, California 94143-2550 (United States); Mobley, David L. [Departments of Pharmaceutical Sciences and Chemistry, University of California Irvine, 147 Bison Modular, Building 515, Irvine, California 92697-0001, USA and Department of Chemistry, University of New Orleans, 2000 Lakeshore Drive, New Orleans, Louisiana 70148 (United States)] [Departments of Pharmaceutical Sciences and Chemistry, University of California Irvine, 147 Bison Modular, Building 515, Irvine, California 92697-0001, USA and Department of Chemistry, University of New Orleans, 2000 Lakeshore Drive, New Orleans, Louisiana 70148 (United States); Dill, Ken A. [Laufer Center for Physical and Quantitative Biology, 5252 Stony Brook University, Stony Brook, New York 11794-0001 (United States)] [Laufer Center for Physical and Quantitative Biology, 5252 Stony Brook University, Stony Brook, New York 11794-0001 (United States); Hünenberger, Philippe H., E-mail: phil@igc.phys.chem.ethz.ch [Laboratory of Physical Chemistry, Swiss Federal Institute of Technology, ETH, 8093 Zürich (Switzerland)
2013-11-14T23:59:59.000Z
The calculation of a protein-ligand binding free energy based on molecular dynamics (MD) simulations generally relies on a thermodynamic cycle in which the ligand is alchemically inserted into the system, both in the solvated protein and free in solution. The corresponding ligand-insertion free energies are typically calculated in nanoscale computational boxes simulated under periodic boundary conditions and considering electrostatic interactions defined by a periodic lattice-sum. This is distinct from the ideal bulk situation of a system of macroscopic size simulated under non-periodic boundary conditions with Coulombic electrostatic interactions. This discrepancy results in finite-size effects, which affect primarily the charging component of the insertion free energy, are dependent on the box size, and can be large when the ligand bears a net charge, especially if the protein is charged as well. This article investigates finite-size effects on calculated charging free energies using as a test case the binding of the ligand 2-amino-5-methylthiazole (net charge +1 e) to a mutant form of yeast cytochrome c peroxidase in water. Considering different charge isoforms of the protein (net charges ?5, 0, +3, or +9 e), either in the absence or the presence of neutralizing counter-ions, and sizes of the cubic computational box (edges ranging from 7.42 to 11.02 nm), the potentially large magnitude of finite-size effects on the raw charging free energies (up to 17.1 kJ?mol{sup ?1}) is demonstrated. Two correction schemes are then proposed to eliminate these effects, a numerical and an analytical one. Both schemes are based on a continuum-electrostatics analysis and require performing Poisson-Boltzmann (PB) calculations on the protein-ligand system. While the numerical scheme requires PB calculations under both non-periodic and periodic boundary conditions, the latter at the box size considered in the MD simulations, the analytical scheme only requires three non-periodic PB calculations for a given system, its dependence on the box size being analytical. The latter scheme also provides insight into the physical origin of the finite-size effects. These two schemes also encompass a correction for discrete solvent effects that persists even in the limit of infinite box sizes. Application of either scheme essentially eliminates the size dependence of the corrected charging free energies (maximal deviation of 1.5 kJ?mol{sup ?1}). Because it is simple to apply, the analytical correction scheme offers a general solution to the problem of finite-size effects in free-energy calculations involving charged solutes, as encountered in calculations concerning, e.g., protein-ligand binding, biomolecular association, residue mutation, pK{sub a} and redox potential estimation, substrate transformation, solvation, and solvent-solvent partitioning.
Tahmasebi Birgani, Mohamad J. [Department of Radiation Therapy, Golestan Hospital, JondiShapour University of Medical Science, Ahvaz (Iran, Islamic Republic of); Department of Medical Physics, JondiShapour University of Medical Sciences, Ahvaz (Iran, Islamic Republic of); Chegeni, Nahid, E-mail: nchegen@yahoo.com [Department of Medical Physics, JondiShapour University of Medical Sciences, Ahvaz (Iran, Islamic Republic of); Zabihzadeh, Mansoor; Hamzian, Nima [Department of Medical Physics, JondiShapour University of Medical Sciences, Ahvaz (Iran, Islamic Republic of)
2014-04-01T23:59:59.000Z
Equivalent field is frequently used for central axis depth-dose calculations of rectangular- and irregular-shaped photon beams. As most of the proposed models to calculate the equivalent square field are dosimetry based, a simple physical-based method to calculate the equivalent square field size was used as the basis of this study. The table of the sides of the equivalent square or rectangular fields was constructed and then compared with the well-known tables by BJR and Venselaar, et al. with the average relative error percentage of 2.5 ± 2.5% and 1.5 ± 1.5%, respectively. To evaluate the accuracy of this method, the percentage depth doses (PDDs) were measured for some special irregular symmetric and asymmetric treatment fields and their equivalent squares for Siemens Primus Plus linear accelerator for both energies, 6 and 18 MV. The mean relative differences of PDDs measurement for these fields and their equivalent square was approximately 1% or less. As a result, this method can be employed to calculate equivalent field not only for rectangular fields but also for any irregular symmetric or asymmetric field.
Beta-delayed fission and neutron emission calculations for the actinide cosmochronometers
Meyer, B.S.; Howard, W.M.; Mathews, G.J.; Takahashi, K.; Moeller, P.; Leander, G.A.
1989-05-01T23:59:59.000Z
The Gamow-Teller beta-strength distributions for 19 neutron-rich nuclei, including ten of interest for the production of the actinide cosmochronometers, are computed microscopically with a code that treats nuclear deformation explicitly. The strength distributions are then used to calculate the beta-delayed fission, neutron emission, and gamma deexcitation probabilities for these nuclei. Fission is treated both in the complete damping and WKB approximations for penetrabilities through the nuclear potential-energy surface. The resulting fission probabilities differ by factors of 2 to 3 or more from the results of previous calculations using microscopically computed beta-strength distributions around the region of greatest interest for production of the cosmochronometers. The indications are that a consistent treatment of nuclear deformation, fission barriers, and beta-strength functions is important in the calculation of delayed fission probabilities and the production of the actinide cosmochronometers. Since we show that the results are very sensitive to relatively small changes in model assumptions, large chronometric ages for the Galaxy based upon high beta-delayed fission probabilities derived from an inconsistent set of nuclear data calculations must be considered quite uncertain.
Interaction of loading pattern and nuclear data uncertainties in reactor core calculations
Klein, M.; Gallner, L.; Krzykacz-Hausmann, B.; Pautz, A.; Velkov, K.; Zwermann, W. [Gesellschaft fuer Anlagen- und Reaktorsicherheit GRS MbH, Boltzmannstr. 14, D- 85748 Garching b. Muenchen (Germany)
2012-07-01T23:59:59.000Z
Along with best-estimate calculations for design and safety analysis, understanding uncertainties is important to determine appropriate design margins. In this framework, nuclear data uncertainties and their propagation to full core calculations are a critical issue. To deal with this task, different error propagation techniques, deterministic and stochastic are currently developed to evaluate the uncertainties in the output quantities. Among these is the sampling based uncertainty and sensitivity software XSUSA which is able to quantify the influence of nuclear data covariance on reactor core calculations. In the present work, this software is used to investigate systematically the uncertainties in the power distributions of two PWR core loadings specified in the OECD UAM-Benchmark suite. With help of a statistical sensitivity analysis, the main contributors to the uncertainty are determined. Using this information a method is studied with which loading patterns of reactor cores can be optimized with regard to minimizing power distribution uncertainties. It is shown that this technique is able to halve the calculation uncertainties of a MOX/UOX core configuration. (authors)
Iterative acceleration methods for Monte Carlo and deterministic criticality calculations
Urbatsch, T.J.
1995-11-01T23:59:59.000Z
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.
The first-principle coupled calculations using TMCC and CFX for the pin-wise simulation of LWR
Li, L.; Wang, K. [Dept. of Engineering Physics, Tsinghua Univ., Liuqing Building, Beijing, 100084 (China)
2012-07-01T23:59:59.000Z
The coupling of neutronics and thermal-hydraulics plays an important role in the reactor safety, core design and operation of nuclear power facilities. This paper introduces the research on the coupling of Monte Carlo method and CFD method, specifically using TMCC and CFX. The methods of the coupling including the coupling approach, data transfer, mesh mapping and transient coupling scheme are studied firstly. The coupling of TMCC and CFX for the steady state calculations is studied and described for the single rod model and the 3 x 3 Rod Bundle model. The calculation results prove that the coupling method is feasible and the coupled calculation can be used for steady state calculations. However, the oscillation which occurs during the coupled calculation indicates that this method still needs to be improved for the accuracy. Then the coupling for the transient calculations is also studied and tested by two cases of the steady state and the lost of heat sink. The preliminary results of the transient coupled calculations indicates that the transient coupling with TMCC and CFX is able to simulate the transients but instabilities are occurring. It is also concluded that the transient coupling of TMCC and CFX needs to be improved due to the limitation of computational resource and the difference of time scales. (authors)
Formal Management Review of the Safety Basis Calculations Noncompliance
Altenbach, T J
2008-06-24T23:59:59.000Z
In Reference 1, LLNL identified a failure to adequately implement an institutional commitment concerning administrative requirements governing the documentation of Safety Basis calculations supporting the Documented Safety Analysis (DSA) process for LLNL Hazard Category 2 and Category 3 nuclear facilities. The AB Section has discovered that the administrative requirements of AB procedure AB-006, 'Safety Basis Calculation Procedure for Category 2 and 3 Nuclear Facilities', have not been uniformly or consistently applied in the preparation of Safety Basis calculations for LLNL Hazard Category 2 and 3 Nuclear Facilities. The SEP Associated Director has directed the AB Section to initiate a formal management review of the issue that includes, but is not necessarily limited to the following topics: (1) the basis establishing Ab-006 as a required internal procedure for Safety Basis calculations; (2) how requirements for Safety Basis calculations flow down in the institutional DSA process; (3) the extent to which affected Laboratory organizations have explicitly complied with the requirements of Procedure AB-006; (4) what alternative approaches LLNL organizations has used for Safety Basis calculations and how these alternate approaches compare with Procedure AB-006 requirements; and (5) how to reconcile Safety Basis calculations that were performed before Procedure AB-006 came into existence (i.e., August 2001). The management review2 also includes an extent-of-condition evaluation to determine how widespread the discovered issue is throughout Laboratory organizations responsible for operating nuclear facilities, and to determine if implementation of AB procedures other than AB-006 has been similarly affected. In Reference 2, Corrective Action 1 was established whereby the SEP Directorate will develop a plan for performing a formal management review of the discovered condition, including an extent-of condition evaluation. In Reference 3, a plan was provided to prepare a formal management review, satisfying Corrective Action 1. An AB-006 Working Group was formed,led by the AB Section, with representatives from the Nuclear Materials Technology Program (NMTP), the Radioactive and Hazardous Waste Management (RHWM) Division, and the Packaging and Transportation Safety (PATS) Program. The key action of this management review was for Working Group members to conduct an assessment of all safety basis calculations referenced in their respective DSAs. Those assessments were tasked to provide the following information: (1) list which safety basis calculations correctly follow AB-006 and therefore require no additional documentation; (2) identify and list which safety basis calculations do not strictly follow AB-006, these include NMTP Engineering Notes, Engineering Safety Notes, and calculations by organizations external to the nuclear facilities (such as Plant Engineering), subcontractor calculations, and other internally generated calculations. Each of these will be reviewed and listed on a memorandum with the facility manager's (or designee's) signature accepting that calculation for use in the DSA. If any of these calculations are lacking the signature of a technical reviewer, they must also be reviewed for technical content and that review documented per AB-006.
Flow conditions of fresh mortar and concrete in different pipes
Jacobsen, Stefan, E-mail: stefan.jacobsen@ntnu.n [Norwegian University of Science and Technology, Dept of Structural Engineering, Trondheim (Norway); Haugan, Lars; Hammer, Tor Arne [SINTEF Byggforsk AS Building and Infrastructure, Trondheim (Norway); Kalogiannidis, Evangelos [Norwegian University of Science and Technology, Dept of Structural Engineering, Trondheim (Norway)
2009-11-15T23:59:59.000Z
The variation in fresh concrete flow rate over the pipe cross section was investigated on differently coloured and highly flowable concrete mixes flowing through pipes of different materials (rubber, steel, acryl). First, uncoloured (gray) concrete was poured through the pipe and the pipe blocked. Similar but coloured (black) concrete was then poured into the pipe filled with gray concrete, flowing after the gray concrete for a while before being blocked and hardened. The advance of the colouring along the pipe wall (showing boundary flow rate) was observed on the moulded concrete surface appearing after removing the pipe from the hardened concrete. The shapes of the interfaces between uncoloured and coloured concrete (showing variation of flow rate over the pipe cross section) were observed on sawn surfaces of concrete half cylinders cut along the length axes of the concrete-filled pipe. Flow profiles over the pipe cross section were clearly seen with maximum flow rates near the centre of the pipe and low flow rate at the pipe wall (typically rubber pipe with reference concrete without silica fume and/or stabilizers). More plug-shaped profiles, with long slip layers and less variation of flow rate over the cross section, were also seen (typically in smooth acrylic pipes). Flow rate, amount of concrete sticking to the wall after flow and SEM-images of pipe surface roughness were observed, illustrating the problem of testing full scale pumping.
Breuer, G D; Chow, J H; Lindh, C B; Miller, N W; Numrich, F H; Price, W W; Turner, A E; Whitney, R R
1982-09-01T23:59:59.000Z
Improved methods are needed to characterize ac system harmonic behavior for ac filter design for HVDC systems. The purpose of this General Electric Company RP1138 research is to evaluate the present filter design practice and to investigate methods for calculating system harmonic impedances. An overview of ac filter design for HVDC systems and a survey of literature related to filter design have been performed. Two methods for calculating system harmonic impedances have been investigated. In the measurement method, an instrumentation system for measuring system voltage and current has been assembled. Different schemes of using the measurements to calculate system harmonic impedances have been studied. In the analytical method, a procedure to include various operating conditions has been proposed. Computer programs for both methods have been prepared, and the results of the measurement and analytical methods analyzed. A conclusion of the project is that the measurement and analytical methods both provided reasonable results. There are correlations between the measured and analytical results for most harmonics, although there are discrepancies between the assumptions used in the two methods. A sensitivity approach has been proposed to further correlate the results. From the results of the analysis, it is recommended that both methods should be tested further. For the measurement method, more testing should be done to cover different system operating conditions. In the analytical method, more detailed models for representing system components should be studied. In addition, alternative statistical and sensitivity approaches should be attempted.
514 ASHRAE Transactions: Symposia Design cooling load calculation methods are, by the
Handbook--Fundamentals (ASHRAE 1997) and the Cooling and Heating Load Calculation Manual (Mc514 ASHRAE Transactions: Symposia ABSTRACT Design cooling load calculation methods are Load Calculation Methods (942-RP)" are also given. INTRODUCTION Design cooling load calculation
Chen, Y.; Li, X.; Zhang, Q.; Spitler, J.; Fisher, D.
2006-01-01T23:59:59.000Z
Conduction transfer functions (CTFs) are widely used to calculate conduction heat transfer in building cooling load and energy calculations. They can conveniently fit into any load and energy calculation techniques to perform conduction calculations...
Solar Reflectance Index Calculation Worksheet Instructions Usage: The purpose of this calculator is to enable contractors and homeowners to quickly and accurately calculate the solar reflectance product exceeds the Building Energy Efficiency Standards requirement for either the aged solar
Building a World of Difference
Broader source: Energy.gov [DOE]
Waste?to?Energy Roadmapping Workshop Building a World of Difference Presentation by Patricia Scanlan, Director of Residuals Treatment Technologies, Black & Veatch
Individual differences in sentence processing
Troyer, Melissa L
2012-01-01T23:59:59.000Z
This thesis aims to elucidate shared mechanisms between retrieval in sentence processing and memory retrieval processes in nonlinguistic domains using an individual differences approach. Prior research in individual ...
Beryllium Wipe Sampling (differing methods - differing exposure potentials)
Kerr, Kent
2005-03-09T23:59:59.000Z
This research compared three wipe sampling techniques currently used to test for beryllium contamination on room and equipment surfaces in Department of Energy facilities. Efficiencies of removal of beryllium contamination from typical painted surfaces were tested by wipe sampling without a wetting agent, with water-moistened wipe materials, and by methanol-moistened wipes. Analysis indicated that methanol-moistened wipe sampling removed about twice as much beryllium/oil-film surface contamination as water-moistened wipes, which removed about twice as much residue as dry wipes. Criteria at 10 CFR 850.30 and .31 were established on unspecified wipe sampling method(s). The results of this study reveal a need to identify criteria-setting method and equivalency factors. As facilities change wipe sampling methods among the three compared in this study, these results may be useful for approximate correlations. Accurate decontamination decision-making depends on the selection of appropriate wetting agents for the types of residues and surfaces. Evidence for beryllium sensitization via skin exposure argues in favor of wipe sampling with wetting agents that provide enhanced removal efficiency such as methanol when surface contamination includes oil mist residue.
Baer, Howard; Sreethawong, Warintorn [Dept. of Physics and Astronomy, University of Oklahoma, Norman, OK 73019 (United States); Lessa, Andre, E-mail: baer@nhn.ou.edu, E-mail: lessa@fma.if.usp.br, E-mail: wstan@nhn.ou.edu [Instituto de Física, Universidade de São Paulo, São Paulo (Brazil)
2012-01-01T23:59:59.000Z
We calculate the relic abundance of mixed axion/neutralino cold dark matter which arises in R-parity conserving supersymmetric (SUSY) models wherein the strong CP problem is solved by the Peccei-Quinn (PQ) mechanism with a concommitant axion/saxion/axino supermultiplet. By numerically solving the coupled Boltzmann equations, we include the combined effects of 1. thermal axino production with cascade decays to a neutralino LSP, 2. thermal saxion production and production via coherent oscillations along with cascade decays and entropy injection, 3. thermal neutralino production and re-annihilation after both axino and saxion decays, 4. gravitino production and decay and 5. axion production both thermally and via oscillations. For SUSY models with too high a standard neutralino thermal abundance, we find the combined effect of SUSY PQ particles is not enough to lower the neutralino abundance down to its measured value, while at the same time respecting bounds on late-decaying neutral particles from BBN. However, models with a standard neutralino underabundance can now be allowed with either neutralino or axion domination of dark matter, and furthermore, these models can allow the PQ breaking scale f{sub a} to be pushed up into the 10{sup 14}?10{sup 15} GeV range, which is where it is typically expected to be in string theory models.
Ab-initio calculations on two-electron ions in strongly coupled plasma environment
Bhattacharyya, S; Mukherjee, T K
2015-01-01T23:59:59.000Z
In this work, the controversy between the interpretations of recent measurements on dense aluminum plasma created with Linac coherent light sources (LCLS) X-ray free electron laser (FEL) and Orion laser has been addressed. In both kind of experiments, helium-like and hydrogen-like spectral lines are used for plasma diagnostics . However, there exist no precise theoretical calculations for He-like ions within dense plasma environment. The strong need for an accurate theoretical estimates for spectral properties of He-like ions in strongly coupled plasma environment leads us to perform ab initio calculations in the framework of Rayleigh-Ritz variation principle in Hylleraas coordinates where ion-sphere potential is used. An approach to resolve the long-drawn problem of numerical instability for evaluating two-electron integrals with extended basis inside a finite domain is presented here. The present values of electron densities corresponding to disappearance of different spectral lines obtained within the fram...
Benchmark data for validating irradiated fuel compositions used in criticality calculations
Bierman, S.R.; Talbert, R.J.
1994-10-01T23:59:59.000Z
To establish criticality safety margins utilizing burnup credit in the storage and transport of spent reactor fuels requires a knowledge of the uncertainty in the calculated fuel composition used in making the reactivity assessment. To provide data for validating such calculated burnup fuel compositions, radiochemical assays have been obtained as part of the United States Department of Energy From-Reactor Cask Development Program. Assay results and associated operating histories on the initial three samples analyzed in this effort are presented. The three samples were taken from different axial regions of a Pressurized Water Reactor fuel rod and represent radiation exposures of about 37, 27, and 44 GWd/MTU. The data are presented in a benchmark type format to facilitate identification/referencing and computer code input.
Direct Calculation of Ice Homogeneous Nucleation Rate for a Molecular Model of Water
Haji-Akbari, Amir
2015-01-01T23:59:59.000Z
Ice formation is ubiquitous in nature, with important consequences in a variety of systems and environments, including biological cells [1], soil [2], aircraft [3], transportation infrastructure [4] and atmospheric clouds [5,6]. However, its intrinsic kinetics and microscopic mechanism are difficult to discern with current experiments. Molecular simulations of ice nucleation are also challenging, and direct rate calculations have only been performed for coarse-grained models of water [7-9]. For the more realistic molecular models, only indirect estimates have been obtained, e.g.~by assuming the validity of classical nucleation theory [10]. Here, we use a path sampling approach to perform the first direct rate calculation of homogeneous nucleation of ice in a molecular model of water. We use TIP4P/Ice [11], the most accurate among the existing molecular models for studying ice polymorphs. By using a novel topological order parameter for distinguishing different polymorphs, we are able to identify a freezing me...
Sun, Shih-Jye [Department of Applied Physics, National University of Kaohsiung, Kaohsiung 811, Taiwan (China); Lin, Ken-Huang; Li, Jia-Yun [Department of Mechanical and Electro-Mechanical Engineering, National Sun Yat-Sen University, Kaohsiung 804, Taiwan (China); Ju, Shin-Pon, E-mail: jushin-pon@mail.nsysu.edu.tw [Department of Mechanical and Electro-Mechanical Engineering, National Sun Yat-Sen University, Kaohsiung 804, Taiwan (China); Department of Medicinal and Applied Chemistry, Kaohsiung Medical University, Kaohsiung 807, Taiwan (China)
2014-10-07T23:59:59.000Z
The simulated annealing basin-hopping method incorporating the penalty function was used to predict the lowest-energy structures for ultrathin tungsten nanowires and nanotubes of different sizes. These predicted structures indicate that tungsten one-dimensional structures at this small scale do not possess B.C.C. configuration as in bulk tungsten material. In order to analyze the relationship between multi-shell geometries and electronic transfer, the electronic and structural properties of tungsten wires and tubes including partial density of state and band structures which were determined and analyzed by quantum chemistry calculations. In addition, in order to understand the application feasibility of these nanowires and tubes on nano-devices such as field emitters or chemical catalysts, the electronic stability of these ultrathin tungsten nanowires was also investigated by density functional theory calculations.
Hybrid model calculations of direct photons in high-energy nuclear collisions
Björn Bäuchle; Marcus Bleicher
2010-03-04T23:59:59.000Z
Direct photon emission in heavy-ion collisions is calculated within a relativistic micro+macro hybrid model and compared to the microscopic transport model UrQMD. In the hybrid approach, the high-density part of the evolution is replaced by an ideal 3-dimensional hydrodynamic calculation. This allows to examine the effects of viscosity and full local thermalization, in comparison of the transport model to the ideal fluid-dynamics. We study the origin of high-p_T photons as well as the impact of elementary high-sqrt(s) collisions. We further explore the contribution of different production channels and non-thermal radiation to the spectrum of direct photons. Detailed comparison to the measurements by the WA98-collaboration are also undertaken.
Fast plane wave density functional theory molecular dynamics calculations on multi-GPU machines
Jia, Weile, E-mail: jiawl@sccas.cn [Supercomputing Center, Computer Network Information Center, Chinese Academy of Sciences, No. 4 South 4th Street, ZhongGuanCun, Beijing 100190 (China) [Supercomputing Center, Computer Network Information Center, Chinese Academy of Sciences, No. 4 South 4th Street, ZhongGuanCun, Beijing 100190 (China); University of Chinese Academy of Sciences, Beijing (China); Fu, Jiyun, E-mail: fujy@sccas.cn [Supercomputing Center, Computer Network Information Center, Chinese Academy of Sciences, No. 4 South 4th Street, ZhongGuanCun, Beijing 100190 (China) [Supercomputing Center, Computer Network Information Center, Chinese Academy of Sciences, No. 4 South 4th Street, ZhongGuanCun, Beijing 100190 (China); University of Chinese Academy of Sciences, Beijing (China); Cao, Zongyan, E-mail: zycao@sccas.cn [Supercomputing Center, Computer Network Information Center, Chinese Academy of Sciences, No. 4 South 4th Street, ZhongGuanCun, Beijing 100190 (China)] [Supercomputing Center, Computer Network Information Center, Chinese Academy of Sciences, No. 4 South 4th Street, ZhongGuanCun, Beijing 100190 (China); Wang, Long, E-mail: wangl@sccas.cn [Supercomputing Center, Computer Network Information Center, Chinese Academy of Sciences, No. 4 South 4th Street, ZhongGuanCun, Beijing 100190 (China)] [Supercomputing Center, Computer Network Information Center, Chinese Academy of Sciences, No. 4 South 4th Street, ZhongGuanCun, Beijing 100190 (China); Chi, Xuebin, E-mail: chi@sccas.cn [Supercomputing Center, Computer Network Information Center, Chinese Academy of Sciences, No. 4 South 4th Street, ZhongGuanCun, Beijing 100190 (China)] [Supercomputing Center, Computer Network Information Center, Chinese Academy of Sciences, No. 4 South 4th Street, ZhongGuanCun, Beijing 100190 (China); Gao, Weiguo, E-mail: wggao@fudan.edu.cn [School of Mathematical Sciences, Fudan University, 220 Handan Road, Shanghai 200433 (China) [School of Mathematical Sciences, Fudan University, 220 Handan Road, Shanghai 200433 (China); MOE Key Laboratory of Computational Physical Sciences, Fudan University, Shanghai (China); Wang, Lin-Wang, E-mail: lwwang@lbl.gov [Material Science Division, Lawrence Berkeley National Laboratory, One Cyclotron Road Mail Stop 50F Berkeley, CA 94720 (United States)] [Material Science Division, Lawrence Berkeley National Laboratory, One Cyclotron Road Mail Stop 50F Berkeley, CA 94720 (United States)
2013-10-15T23:59:59.000Z
Plane wave pseudopotential (PWP) density functional theory (DFT) calculation is the most widely used method for material simulations, but its absolute speed stagnated due to the inability to use large scale CPU based computers. By a drastic redesign of the algorithm, and moving all the major computation parts into GPU, we have reached a speed of 12 s per molecular dynamics (MD) step for a 512 atom system using 256 GPU cards. This is about 20 times faster than the CPU version of the code regardless of the number of CPU cores used. Our tests and analysis on different GPU platforms and configurations shed lights on the optimal GPU deployments for PWP-DFT calculations. An 1800 step MD simulation is used to study the liquid phase properties of GaInP.
Methods, algorithms and computer codes for calculation of electron-impact excitation parameters
Bogdanovich, P; Stonys, D
2015-01-01T23:59:59.000Z
We describe the computer codes, developed at Vilnius University, for the calculation of electron-impact excitation cross sections, collision strengths, and excitation rates in the plane-wave Born approximation. These codes utilize the multireference atomic wavefunctions which are also adopted to calculate radiative transition parameters of complex many-electron ions. This leads to consistent data sets suitable in plasma modelling codes. Two versions of electron scattering codes are considered in the present work, both of them employing configuration interaction method for inclusion of correlation effects and Breit-Pauli approximation to account for relativistic effects. These versions differ only by one-electron radial orbitals, where the first one employs the non-relativistic numerical radial orbitals, while another version uses the quasirelativistic radial orbitals. The accuracy of produced results is assessed by comparing radiative transition and electron-impact excitation data for neutral hydrogen, helium...
Benchmark calculations for elastic fermion-dimer scattering
Shahin Bour; H. -W. Hammer; Dean Lee; Ulf-G. Meißner
2012-06-08T23:59:59.000Z
We present continuum and lattice calculations for elastic scattering between a fermion and a bound dimer in the shallow binding limit. For the continuum calculation we use the Skorniakov-Ter-Martirosian (STM) integral equation to determine the scattering length and effective range parameter to high precision. For the lattice calculation we use the finite-volume method of L\\"uscher. We take into account topological finite-volume corrections to the dimer binding energy which depend on the momentum of the dimer. After subtracting these effects, we find from the lattice calculation kappa a_fd = 1.174(9) and kappa r_fd = -0.029(13). These results agree well with the continuum values kappa a_fd = 1.17907(1) and kappa r_fd = -0.0383(3) obtained from the STM equation. We discuss applications to cold atomic Fermi gases, deuteron-neutron scattering in the spin-quartet channel, and lattice calculations of scattering for nuclei and hadronic molecules at finite volume.
Kim, Philip
Tooling Factor Calculation In order to yield a more accurate indication of a deposited film's thickness, the rate monitor's tooling factor attempts to compensate for necessary differences member before changing an established tooling factor. 1. Position a sample, masked on a half
Boyer, Edmond
Dynamical mean-field theory using Wannier functions: A flexible route to electronic structure materials with different degrees of structural and electronic complexity, SrVO3 and BaVS3, are investigated calculations of strongly correlated materials F. Lechermann,1,2, * A. Georges,1 A. Poteryaev,1 S. Biermann,1 M
Napier, B.A.
1992-12-01T23:59:59.000Z
A series of scoping calculations has been undertaken to evaluate the absolute and relative contributions of different radionuclides and exposure pathways to doses that may have been received by individuals living in the vicinity of the Hanford Site. This scoping calculation (Calculation 003) examined the contributions of numerous radionuclides to dose via environmental exposures and accumulation in foods. This study builds on the work initiated in the first scoping study of iodine in cow`s milk (calculation 001). Addressed in this calculation were the contributions to organ and effective dose of infants and adults from (1) air submersion and groundshine external dose, (2) inhalation, (3) ingestion of soil by humans, (4) ingestion of leafy vegetables, (5) ingestion of other vegetables and fruits, (6) ingestion of meat, (7) ingestion of eggs, and (8) ingestion of cows` milk from Feeding Regime 1, as described in Calculation 001.
Ramos-Mendez, Jose [Benemerita Universidad Autonoma de Puebla, 18 Sur and San Claudio Avenue, Puebla, Puebla 72750 (Mexico); Perl, Joseph [SLAC National Accelerator Laboratory, 2575 Sand Hill Road, Menlo Park, California 94025 (United States); Faddegon, Bruce [Department of Radiation Oncology, University of California at San Francisco, California 94143 (United States); Schuemann, Jan; Paganetti, Harald [Department of Radiation Oncology, Massachusetts General Hospital and Harvard Medical School, Boston, Massachusetts 02114 (United States)
2013-04-15T23:59:59.000Z
Purpose: To present the implementation and validation of a geometrical based variance reduction technique for the calculation of phase space data for proton therapy dose calculation. Methods: The treatment heads at the Francis H Burr Proton Therapy Center were modeled with a new Monte Carlo tool (TOPAS based on Geant4). For variance reduction purposes, two particle-splitting planes were implemented. First, the particles were split upstream of the second scatterer or at the second ionization chamber. Then, particles reaching another plane immediately upstream of the field specific aperture were split again. In each case, particles were split by a factor of 8. At the second ionization chamber and at the latter plane, the cylindrical symmetry of the proton beam was exploited to position the split particles at randomly spaced locations rotated around the beam axis. Phase space data in IAEA format were recorded at the treatment head exit and the computational efficiency was calculated. Depth-dose curves and beam profiles were analyzed. Dose distributions were compared for a voxelized water phantom for different treatment fields for both the reference and optimized simulations. In addition, dose in two patients was simulated with and without particle splitting to compare the efficiency and accuracy of the technique. Results: A normalized computational efficiency gain of a factor of 10-20.3 was reached for phase space calculations for the different treatment head options simulated. Depth-dose curves and beam profiles were in reasonable agreement with the simulation done without splitting: within 1% for depth-dose with an average difference of (0.2 {+-} 0.4)%, 1 standard deviation, and a 0.3% statistical uncertainty of the simulations in the high dose region; 1.6% for planar fluence with an average difference of (0.4 {+-} 0.5)% and a statistical uncertainty of 0.3% in the high fluence region. The percentage differences between dose distributions in water for simulations done with and without particle splitting were within the accepted clinical tolerance of 2%, with a 0.4% statistical uncertainty. For the two patient geometries considered, head and prostate, the efficiency gain was 20.9 and 14.7, respectively, with the percentages of voxels with gamma indices lower than unity 98.9% and 99.7%, respectively, using 2% and 2 mm criteria. Conclusions: The authors have implemented an efficient variance reduction technique with significant speed improvements for proton Monte Carlo simulations. The method can be transferred to other codes and other treatment heads.
Can fusion coefficients be calculated from the depth rule ?
A. N. Kirillov; P. Mathieu; D. Senechal; M. Walton
1992-09-28T23:59:59.000Z
The depth rule is a level truncation of tensor product coefficients expected to be sufficient for the evaluation of fusion coefficients. We reformulate the depth rule in a precise way, and show how, in principle, it can be used to calculate fusion coefficients. However, we argue that the computation of the depth itself, in terms of which the constraints on tensor product coefficients is formulated, is problematic. Indeed, the elements of the basis of states convenient for calculating tensor product coefficients do not have a well-defined depth! We proceed by showing how one can calculate the depth in an `approximate' way and derive accurate lower bounds for the minimum level at which a coupling appears. It turns out that this method yields exact results for $\\widehat{su}(3)$ and constitutes an efficient and simple algorithm for computing $\\widehat{su}(3)$ fusion coefficients.
Overview of TRAC-PD2 assessment calculations
Waterman, M E
1985-11-01T23:59:59.000Z
A summary of Transient Reactor Analysis Code Version PD2 (TRAC-PD2) calculations performed at the Idaho National Engineering Laboratory (INEL) is presented in this report as part of the US Nuclear Regulatory Commission's (NRCs) overall assessment program of TRAC-PD2. The calculated and measured parameters summarized in this report are break mass flow rate, primary coolant system pressure, reactor core flow rates, and fuel rod cladding temperatures. The data were obtained from seven tests that were performed at two test facilities. The tests were conducted to study the various aspects of cold leg break transients, including the effects of large and small beaks, and core reflood phenomena. User experience gained from the various calculations is also summarized. 42 figs., 10 tabs.
Simple program calculates partial liquid volumes in vessels
Koch, P.
1992-04-13T23:59:59.000Z
This paper reports on a simple calculator program which solves problems of partial liquid volumes for a variety of storage and process vessels, including inclined cylindrical vessels and those with conical heads. Engineers in the oil refining and chemical industries are often confronted with the problem of estimating partial liquid volumes in storage tanks or process vessels. Cistern, the calculator program presented here, allows fast and accurate resolution of problems for a wide range of vessels without user intervention, other than inputting the problem data. Running the program requires no mathematical skills. Cistern is written for Hewlett-Packard HP 41CV or HP 41CX programmable calculators (or HP 41C with extended memory modules).
Indoor design condition and the cooling load calculation
Sun, T.Y. [Sun (Tseng-Yao), Rancho Palos Verde, CA (United States)
1997-12-01T23:59:59.000Z
Cooling load calculation involves two steps. The first is to determine the basic building load. This consists of external loads through the building envelope and internal loads from people, lights, appliances, and other heat sources. The required supply air quantity for each conditioned space generally is determined in the first step. This is because each relates only to the coil leaving and required room dry bulb temperatures (unless reheat is required to control the humidity level in the conditioned space). The second step, after completing the above, is to calculate the system cooling load. This step adapts the selected air distribution system to the building load and involves the introduction of the required outdoor air volume into the air conditioning system for ventilation. Proper psychrometric analysis is required to calculate the entering and leaving wet bulb conditions of the air passing through the cooling coil. These, together with the corresponding dry bulb temperatures, will determine the system cooling load.
On calculation of microlensing light curve by gravitational lens caustic
M. B. Bogdanov
2001-02-02T23:59:59.000Z
For an analysis of microlensing observational data in case of binary gravitational lenses as well as for an interpretation of observations of high magnification events in multiple images of a lensed quasar it is necessary to calculate for a given source the microlensing light curve by a fold caustic. This problem comes to the numerical calculation of a singular integral. We formulated the sufficient condition of a convergence of the integral sum for this singular integral. The strictly approach to the problem of a comparison of model results with the unequally sampled observational data consists in calculation of the model light curve in equidistant points of the canonical dissection of the integration segment and a following interpolation of its values at the moments of observations.
Excited State Effects in Nucleon Matrix Element Calculations
Constantia Alexandrou, Martha Constantinou, Simon Dinter, Vincent Drach, Karl Jansen, Theodoros Leontiou, Dru B Renner
2011-12-01T23:59:59.000Z
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.
Equation calculates activated carbon's capacity for adsorbing pollutants
Yaws, C.L.; Bu, L.; Nijhawan, S. (Lamar Univ., Beaumont, TX (United States))
1995-02-13T23:59:59.000Z
Adsorption on activated carbon is an effective method for removing volatile organic compound (VOC) contaminants from gases. A new, simple equation has been developed for calculating activated carbon's adsorption capacity as a function of the VOC concentration in the gas. The correlation shows good agreement with experimental results. Results from the equation are applicable for conditions commonly encountered in air pollution control techniques (25 C, 1 atm). The only input parameters needed are VOC concentrations and a table of correlation coefficients for 292 C[sub 8]-C[sub 14] compounds. The table is suitable for rapid engineering usage with a personal computer or hand calculator.
Recent Advances in Shell Evolution with Shell-Model Calculations
Yutaka Utsuno; Takaharu Otsuka; Yusuke Tsunoda; Noritaka Shimizu; Michio Honma; Tomoaki Togashi; Takahiro Mizusaki
2014-09-16T23:59:59.000Z
Shell evolution in exotic nuclei is investigated with large-scale shell-model calculations. After presenting that the central and tensor forces produce distinctive ways of shell evolution, we show several recent results: (i) evolution of single-particle-like levels in antimony and cupper isotopes, (ii) shape coexistence in nickel isotopes understood in terms of configuration-dependent shell structure, and (iii) prediction of the evolution of the recently established $N=34$ magic number towards smaller proton numbers. In any case, large-scale shell-model calculations play indispensable roles in describing the interplay between single-particle character and correlation.
Phenomenological method of calculating microwave longitudinal coupling impedances
Giordano, S.; Votruba, J.
1980-05-01T23:59:59.000Z
A previous paper described an investigation of the longitudinal coupling impedance of the TM/sub olm/ modes in the ISA vacuum chamber. A method was developed for calculating these impedances by using the data derived from pertubation measurements. This method gave accurate results between 2.6 and 2.8 GHz, but above 2.8 GHz measurements became difficult because of the mixing of the TM/sub olm/ modes with other modes. This paper presents a phenomenological approach for calculating these impedances based on previously developed concepts.
A Parallel Orbital-Updating Approach for Electronic Structure Calculations
Xiaoying Dai; Xingao Gong; Aihui Zhou; Jinwei Zhu
2014-11-05T23:59:59.000Z
In this paper, we propose an orbital iteration based parallel approach for electronic structure calculations. This approach is based on our understanding of the single-particle equations of independent particles that move in an effective potential. With this new approach, the solution of the single-particle equation is reduced to some solutions of independent linear algebraic systems and a small scale algebraic problem. It is demonstrated by our numerical experiments that this new approach is quite efficient for full-potential calculations for a class of molecular systems.
Semiclassical framework for the calculation of transport anisotropies
Vyborny, Karel; Kovalev, Alexey A.; Sinova, Jairo; Jungwirth, T.
2009-01-01T23:59:59.000Z
microscopic calculations and a simple physical model was recently found in the diluted magnetic semiconductor10,11 #1;Ga,Mn#2;As whose band structure is much simpler. Despite the long history of the AMR research, the ques- tion has not been answered... the main body of the paper by discussing the relevance of our model calculations for the AMR in magnetic semiconductors and by summarizing the key elements of the theoretical framework we have developed. Appendixes A?G contain de- tails of our...
Calculation of the strange quark mass using domain wall fermions
Tom Blum; Amarjit Soni; Matthew Wingate
2000-09-18T23:59:59.000Z
We present a first calculation of the strange quark mass using domain wall fermions. This paper contains an overview of the domain wall discretization and a pedagogical presentation of the perturbative calculation necessary for computing the mass renormalization. We combine the latter with numerical simulations to estimate the strange quark mass. Our final result in the quenched approximation is 95(26) MeV in the ${\\bar{MS}}$ scheme at a scale of 2 GeV. We find that domain wall fermions have a small perturbative mass renormalization, similar to Wilson quarks, and exhibit good scaling behavior.
Heat Transfer Calculations for a Fixed CST Bed Column
Lee, S.Y.
2001-03-28T23:59:59.000Z
In support of the crystalline silicotitanate (CST) ion exchange project of High-Level Waste (HLW) Process Engineering, a transient two-dimensional heat transfer model that includes the conduction process neglecting the convection cooling mechanism inside the CST column has been constructed and heat transfer calculations made for the present design configurations. For this situation, a no process flow condition through the column was assumed as one of the reference conditions for the simulation of a loss-of-flow accident. The modeling and calculations were performed using a computational heat transfer approach.
Hand-held calculator program gives economic evaluation
Jones, R.; Maxwell, R.L.
1983-02-14T23:59:59.000Z
This article presents a comprehensive oil and gas property written for the Hewlett-Packard 41CV handheld calculator (or an HP-41C equipped with 4 memory modules). The program allows the user to enter all of the required parameters at the beginning and calculates the results with a minimum of interruptions. This is accomplished by tieing an engineering projection of future production to the desired variations in the economic factors to be used in the evaluation process. The presented economic analysis program can be used for a variety of economic and reserve evaluations.
Li, Yue; Duan, Yan-Ping, E-mail: duanyanping@tongji.edu.cn; Huang, Fan; Yang, Jing; Xiang, Nan; Meng, Xiang-Zhou; Chen, Ling
2014-06-01T23:59:59.000Z
Highlights: • PBDEs were detected in the majority of e-waste. • PBDEs were found in TVs made in China after 1990. • The levels of ?PBDEs in e-waste made in Japan far exceed the threshold limit of RoHS. • The inappropriate recycling and disposal of e-waste is an important source of PBDEs. - Abstract: Very few data for polybrominated diphenyl ethers (PBDEs) were available in the electronic waste (e-waste) as one of the most PBDEs emission source. This study reported concentrations of PBDEs in e-waste including printer, rice cooker, computer monitor, TV, electric iron and water dispenser, as well as dust from e-waste, e-waste dismantling workshop and surface soil from inside and outside of an e-waste recycling plant in Shanghai, Eastern China. The results showed that PBDEs were detected in the majority of e-waste, and the concentrations of ?PBDEs ranged from not detected to 175 g/kg, with a mean value of 10.8 g/kg. PBDEs were found in TVs made in China after 1990. The mean concentrations of ?PBDEs in e-waste made in Korea, Japan, Singapore and China were 1.84 g/kg, 20.5 g/kg, 0.91 g/kg, 4.48 g/kg, respectively. The levels of ?PBDEs in e-waste made in Japan far exceed the threshold limit of RoHS (1.00 g/kg). BDE-209 dominated in e-waste, accounting for over 93%. The compositional patterns of PBDEs congeners resembled the profile of Saytex 102E, indicating the source of deca-BDE. Among the samples of dust and surface soil from a typical e-waste recycling site, the highest concentrations of ?{sub 18}PBDEs and BDE-209 were found in dust in e-waste, ranging from 1960 to 340,710 ng/g and from 910 to 320,400 ng/g, which were 1–2 orders of magnitude higher than other samples. It suggested that PBDEs released from e-waste via dust, and then transferred to surrounding environment.
James, Scott; Cohan, Alexander [Sandia National Laboratories, Albuquerque, NM] [Sandia National Laboratories, Albuquerque, NM
2005-08-01T23:59:59.000Z
Given pre-existing Groundwater Modeling System (GMS) models of the Horonobe Underground Research Laboratory (URL) at both the regional and site scales, this work performs an example uncertainty analysis for performance assessment (PA) applications. After a general overview of uncertainty and sensitivity analysis techniques, the existing GMS site-scale model is converted to a PA model of the steady-state conditions expected after URL closure. This is done to examine the impact of uncertainty in site-specific data in conjunction with conceptual model uncertainty regarding the location of the Oomagari Fault. A heterogeneous stochastic model is developed and corresponding flow fields and particle tracks are calculated. In addition, a quantitative analysis of the ratio of dispersive to advective forces, the F-ratio, is performed for stochastic realizations of each conceptual model. Finally, a one-dimensional transport abstraction is modeled based on the particle path lengths and the materials through which each particle passes to yield breakthrough curves at the model boundary. All analyses indicate that accurate characterization of the Oomagari Fault with respect to both location and hydraulic conductivity is critical to PA calculations. This work defines and outlines typical uncertainty and sensitivity analysis procedures and demonstrates them with example PA calculations relevant to the Horonobe URL. Acknowledgement: This project was funded by Japan Nuclear Cycle Development Institute (JNC). This work was conducted jointly between Sandia National Laboratories (SNL) and JNC under a joint JNC/U.S. Department of Energy (DOE) work agreement. Performance assessment calculations were conducted and analyzed at SNL based on a preliminary model by Kashima, Quintessa, and JNC and include significant input from JNC to make sure the results are relevant for the Japanese nuclear waste program.
Some differences between Dirac's hole theory and quantum field theory
Dan Solomon
2005-06-30T23:59:59.000Z
Diracs hole theory (HT) and quantum field theory (QFT) are generally considered to be equivalent to each other. However, it has been recently shown by several researchers that this is not necessarily the case. When the change in the vacuum energy was calculated for a time independent perturbation HT and QFT yielded different results. In this paper we extend this discussion to include a time dependent perturbation for which the exact solution to the Dirac equation is known. It will be shown that for this case, also, HT and QFT yield different results. In addition, there will be some discussion of the problem of anomalies in QFT.
Ruth, M.; Timbario, T. A.; Timbario, T. J.; Laffen, M.
2011-01-01T23:59:59.000Z
Currently, several cost-per-mile calculators exist that can provide estimates of acquisition and operating costs for consumers and fleets. However, these calculators are limited in their ability to determine the difference in cost per mile for consumer versus fleet ownership, to calculate the costs beyond one ownership period, to show the sensitivity of the cost per mile to the annual vehicle miles traveled (VMT), and to estimate future increases in operating and ownership costs. Oftentimes, these tools apply a constant percentage increase over the time period of vehicle operation, or in some cases, no increase in direct costs at all over time. A more accurate cost-per-mile calculator has been developed that allows the user to analyze these costs for both consumers and fleets. The calculator was developed to allow simultaneous comparisons of conventional light-duty internal combustion engine (ICE) vehicles, mild and full hybrid electric vehicles (HEVs), and fuel cell vehicles (FCVs). This paper is a summary of the development by the authors of a more accurate cost-per-mile calculator that allows the user to analyze vehicle acquisition and operating costs for both consumer and fleets. Cost-per-mile results are reported for consumer-operated vehicles travelling 15,000 miles per year and for fleets travelling 25,000 miles per year.
Appalakondaiah, S.; Vaitheeswaran, G., E-mail: gvaithee@gmail.com [Advanced Centre of Research in High Energy Materials (ACRHEM), University of Hyderabad, Prof. C. R. Rao Road, Gachibowli, Hyderabad 500 046, Andhra Pradesh (India); Lebègue, S. [Laboratoire de Cristallographie, Résonance Magnétique et Modélisations (CRM2, UMR CNRS 7036), Institut Jean Barriol, Université de Lorraine, BP 239, Boulevard des Aiguillettes, 54506 Vandoeuvre-lès-Nancy (France)] [Laboratoire de Cristallographie, Résonance Magnétique et Modélisations (CRM2, UMR CNRS 7036), Institut Jean Barriol, Université de Lorraine, BP 239, Boulevard des Aiguillettes, 54506 Vandoeuvre-lès-Nancy (France)
2014-01-07T23:59:59.000Z
The effects of pressure on the structural and vibrational properties of the layered molecular crystal 1,1-diamino-2,2-dinitroethelene (FOX-7) are explored by first principles calculations. We observe significant changes in the calculated structural properties with different corrections for treating van der Waals interactions to Density Functional Theory (DFT), as compared with standard DFT functionals. In particular, the calculated ground state lattice parameters, volume and bulk modulus obtained with Grimme's scheme, are found to agree well with experiments. The calculated vibrational frequencies demonstrate the dependence of the intra and inter-molecular interactions on FOX-7 under pressure. In addition, we also found a significant increment in the N–H...O hydrogen bond strength under compression. This is explained by the change in bond lengths between nitrogen, hydrogen, and oxygen atoms, as well as calculated IR spectra under pressure. Finally, the computed band gap is about 2.3 eV with generalized gradient approximation, and is enhanced to 5.1 eV with the GW approximation, which reveals the importance of performing quasiparticle calculations in high energy density materials.
Thermonuclear reaction rate of $^{18}$Ne($?$,$p$)$^{21}$Na from Monte-Carlo calculations
P. Mohr; R. Longland; C. Iliadis
2014-12-14T23:59:59.000Z
The $^{18}$Ne($\\alpha$,$p$)$^{21}$Na reaction impacts the break-out from the hot CNO-cycles to the $rp$-process in type I X-ray bursts. We present a revised thermonuclear reaction rate, which is based on the latest experimental data. The new rate is derived from Monte-Carlo calculations, taking into account the uncertainties of all nuclear physics input quantities. In addition, we present the reaction rate uncertainty and probability density versus temperature. Our results are also consistent with estimates obtained using different indirect approaches.
Thermonuclear reaction rate of $^{18}$Ne($\\alpha$,$p$)$^{21}$Na from Monte-Carlo calculations
Mohr, P; Iliadis, C
2014-01-01T23:59:59.000Z
The $^{18}$Ne($\\alpha$,$p$)$^{21}$Na reaction impacts the break-out from the hot CNO-cycles to the $rp$-process in type I X-ray bursts. We present a revised thermonuclear reaction rate, which is based on the latest experimental data. The new rate is derived from Monte-Carlo calculations, taking into account the uncertainties of all nuclear physics input quantities. In addition, we present the reaction rate uncertainty and probability density versus temperature. Our results are also consistent with estimates obtained using different indirect approaches.
GPA CALCULATION GPA = QUALITY POINTS DIVIDED BY QUALITY HOURS
Lawrence, Rick L.
. THIS IS THE TOTAL QUALITY POINTS THAT YOU THINK YOU WILL EARN THIS SEMESTER. TO PLAY WHAT IFGPA CALCULATION WORKSHEET GPA = QUALITY POINTS DIVIDED BY QUALITY HOURS #1 QUALITY HOURS (THROUGH LAST TERM) = __________ #2 QUALITY POINTS (THROUGH LAST TERM) = __________ #3 QUALTIY HOURS CURRENTLY
Calculation of Extreme Wave Loads on Coastal Highway Bridges
Meng, Bo
2010-01-14T23:59:59.000Z
force on bridge decks. 2D Model is a linear wave model, which has the capability of calculating wave velocity potential components in time domain based on wave parameters such as wave height, wave period and water depth, and complex structural geometries...
Wind energy calculated from SAR and scatterometer satellite data
Slide no. The WAsP icon #12;1 8 Slide no. Wind observations #12;1 9 Slide no. European Wind Atlas #121 Slide no. 4 Wind energy calculated from SAR and scatterometer satellite data Charlotte Bay, Italy, 23-24 June 2003 #12;2 Slide no. 4 Presentation Â· RisÃ¸ National Laboratory/ Wind Energy Dept
Atomic Structure Calculations from the Los Alamos Atomic Physics Codes
DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]
Cowan, R. D.
The well known Hartree-Fock method of R.D. Cowan, developed at Los Alamos National Laboratory, is used for the atomic structure calculations. Electron impact excitation cross sections are calculated using either the distorted wave approximation (DWA) or the first order many body theory (FOMBT). Electron impact ionization cross sections can be calculated using the scaled hydrogenic method developed by Sampson and co-workers, the binary encounter method or the distorted wave method. Photoionization cross sections and, where appropriate, autoionizations are also calculated. Original manuals for the atomic structure code, the collisional excitation code, and the ionization code, are available from this website. Using the specialized interface, you will be able to define the ionization stage of an element and pick the initial and final configurations. You will be led through a series of web pages ending with a display of results in the form of cross sections, collision strengths or rates coefficients. Results are available in tabular and graphic form.
ELECTROMOTION 2009 3D Analytical Calculation of Forces between
Paris-Sud XI, UniversitÃ© de
Co or NdFeB, the designers can use magnets owning a really rigid magnetization. They are the magnets whichELECTROMOTION 2009 1 3D Analytical Calculation of Forces between Linear Halbach-Type Permanent Magnet Arrays H. Allag1,2 , J-P. Yonnet1 and M. E. H. Latreche2 1- Laboratoire de GÃ©nie Electrique de
Calculation Method of Permanent Magnet Pickups for Electric Guitars
Paris-Sud XI, UniversitÃ© de
in the 1930s, when Rickenbacker fitted out a guitar with a magnet and coils, thus designing the first magnetic to look at the types of magnetic circuit for the guitar pickups. We consider in this paper the most usual1 Calculation Method of Permanent Magnet Pickups for Electric Guitars G. Lemarquand and V
Bohr Model Calculations for Atoms and Ions Frank Rioux
Rioux, Frank
in doing energy audits, carrying out simple variational calculations and critically analyzing := V12 R1( ) 1 17 R1 := #12;The next step is to do an energy audit for the atom or ion under Department of Chemistry College of St. Benedict| St. Johns University
Efficient Calculation of Statistical Moments for Structural Health Monitoring
Sweetman, Bert
Efficient Calculation of Statistical Moments for Structural Health Monitoring Myoungkeun Choi sen- sor packages have shown considerable promise in providing low-cost Structural Health Monitoring@tamu.edu, Telephone:(409) 740-4834, Fax:(409) 741-7153 1 Journal of Structural Health Monitoring, January 1, 2010, Vol
Calculation of burnup of a black neutron absorber
Yudkevich, M. S., E-mail: umark@adis.vver.kiae.ru [Russian Research Centre Kurchatov Institute (Russian Federation)
2011-12-15T23:59:59.000Z
The procedure of calculation of burnup of fuel and strong neutron absorber in a nuclear reactor is described. The method proposed here makes it possible to avoid difficulties associated with heterogeneous blocking of the absorption cross section. The effectiveness of the method is demonstrated by an example.
EQ6 Calculations for Chemical Degradation of Navy Waste Packages
S. LeStrange
1999-11-15T23:59:59.000Z
The Monitored Geologic Repository Waste Package Operations of the Civilian Radioactive Waste Management System Management & Operating Contractor (CRWMS M&O) performed calculations to provide input for disposal of spent nuclear fuel (SNF) from the Navy (Refs. 1 and 2). The Navy SNF has been considered for disposal at the potential Yucca Mountain site. For some waste packages, the containment may breach (Ref. 3), allowing the influx of water. Water in the waste package may moderate neutrons, increasing the likelihood of a criticality event within the waste package. The water may gradually leach the fissile components and neutron absorbers out of the waste package. In addition, the accumulation of silica (SiO{sub 2}) in the waste package over time may further affect the neutronics of the system. This study presents calculations of the long-term geochemical behavior of waste packages containing the Enhanced Design Alternative (EDA) II inner shell, Navy canister, and basket components. The calculations do not include the Navy SNF in the waste package. The specific study objectives were to determine the chemical composition of the water and the quantity of silicon (Si) and other solid corrosion products in the waste package during the first million years after the waste package is breached. The results of this calculation will be used to ensure that the type and amount of criticality control material used in the waste package design will prevent criticality.
Using Graphical Representations to Support the Calculation of Infusion Parameters
Subramanian, Sriram
Using Graphical Representations to Support the Calculation of Infusion Parameters Sandy J. J. Gould in which participants were asked to solve a num- ber of infusion parameter problems that were represented representations transfer to actual workplace settings. Keywords: Graphical reasoning, infusion pumps, re
Calculating coherent pair production with Monte Carlo methods
Bottcher, C.; Strayer, M.R.
1989-01-01T23:59:59.000Z
We discuss calculations of the coherent electromagnetic pair production in ultra-relativistic hadron collisions. This type of production, in lowest order, is obtained from three diagrams which contain two virtual photons. We discuss simple Monte Carlo methods for evaluating these classes of diagrams without recourse to involved algebraic reduction schemes. 19 refs., 11 figs.
RZ calculations for self shielded multigroup cross sections
Li, M.; Sanchez, R.; Zmijarevic, I.; Stankovski, Z. [Commissariat a l'Energie Atomique CEA, Direction de l'Energie Nucleaire, DEN/DM2S/SERMA/LENR, 91191 Gif-sur-Yvette Cedex (France)
2006-07-01T23:59:59.000Z
A collision probability method has been implemented for RZ geometries. The method accounts for white albedo, specular and translation boundary condition on the top and bottom surfaces of the geometry and for a white albedo condition on the outer radial surface. We have applied the RZ CP method to the calculation of multigroup self shielded cross sections for Gadolinia absorbers in BWRs. (authors)
Ironless Permanent Magnet Motors: Three-Dimensional Analytical Calculation
Paris-Sud XI, Université de
of the magnetic torque exerted between a tile permanent magnet radially magnetized and a winding in ironless structures. Such an expression can be used for calculating the magnetic torque transmitted between the stator or winding dimensions. The ironless structure we consider in this paper is commonly used for high speed
Adaptive Calculation of Variable Coefficients Elliptic Differential Equations via Wavelets
Averbuch, Amir
Description Generating a "good" discrete representation for continuous operators is one of the basic problemsAdaptive Calculation of Variable Coefficients Elliptic Differential Equations via Wavelets Amir rather than in the original physical space can speed up the performance of the sparse solver by a factor
AI A A-90-0688 Multigrid Euler Calculations
Jameson, Antony
the three-dimensional Euler equations is applied to cascade calculation. Test cases of a VKI turbine cascade on blade surfaces show good agreements with experimental data at design conditions, while dis- crepancy support the theory that the development of passage and horse-shoe vortices in cascades is, to a large
Alternative similarity renormalization group generators in nuclear structure calculations
Nuiok M. Dicaire; Conor Omand; Petr Navratil
2014-08-22T23:59:59.000Z
The similarity renormalization group (SRG) has been successfully applied to soften interactions for ab initio nuclear calculations. In almost all practical applications in nuclear physics, an SRG generator with the kinetic energy operator is used. With this choice, a fast convergence of many-body calculations can be achieved, but at the same time substantial three-body interactions are induced even if one starts from a purely two-nucleon (NN) Hamiltonian. Three-nucleon (3N) interactions can be handled by modern many-body methods. However, it has been observed that when including initial chiral 3N forces in the Hamiltonian, the SRG transformations induce a non-negligible four-nucleon interaction that cannot be currently included in the calculations for technical reasons. Consequently, it is essential to investigate alternative SRG generators that might suppress the induction of many-body forces while at the same time might preserve the good convergence. In this work we test two alternative generators with operators of block structure in the harmonic oscillator basis. In the no-core shell model calculations for 3H, 4He and 6Li with chiral NN force, we demonstrate that their performances appear quite promising.
AIM: Web-Based, Residential Energy Calculator for Homeowners
Marshall, K.; Moss, M.; Liu, B.; Culp, C.; Haberl, J.; Herbert, C.
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...
Revised Transition Probabilities for Fe XXV Relativistic CI Calculations
Johnson, Walter R.
Revised Transition Probabilities for Fe XXV Relativistic CI Calculations W. R. Johnson1 and U are provided for transition probabilities between fine-structure components of levels with n 6 in FeXXV. Earlier published data for transitions between fine-structure levels in FeXXV is found to in error
Fuzzy-probabilistic calculations of water-balance uncertainty
Faybishenko, B.
2009-10-01T23:59:59.000Z
Hydrogeological systems are often characterized by imprecise, vague, inconsistent, incomplete, or subjective information, which may limit the application of conventional stochastic methods in predicting hydrogeologic conditions and associated uncertainty. Instead, redictions and uncertainty analysis can be made using uncertain input parameters expressed as probability boxes, intervals, and fuzzy numbers. The objective of this paper is to present the theory for, and a case study as an application of, the fuzzyprobabilistic approach, ombining probability and possibility theory for simulating soil water balance and assessing associated uncertainty in the components of a simple waterbalance equation. The application of this approach is demonstrated using calculations with the RAMAS Risk Calc code, to ssess the propagation of uncertainty in calculating potential evapotranspiration, actual evapotranspiration, and infiltration-in a case study at the Hanford site, Washington, USA. Propagation of uncertainty into the results of water-balance calculations was evaluated by hanging he types of models of uncertainty incorporated into various input parameters. The results of these fuzzy-probabilistic calculations are compared to the conventional Monte Carlo simulation approach and estimates from field observations at the Hanford site.
Patent Citation Analysis: Calculating Science linkage based on Citing Motivation
Menczer, Filippo
1 Patent Citation Analysis: Calculating Science linkage based on Citing Motivation Rui Li used patent bibliometric indicator to measure patent linkage to scientific research based on the frequency of citations to scientific papers within the patent. Science linkage is also regarded as noisy
Solution of Large Eigenvalue Problems in Electronic Structure Calculations \\Lambda
Stathopoulos, Andreas
Solution of Large Eigenvalue Problems in Electronic Structure Calculations \\Lambda Y. Saad y , A the structural and electronic properties of complex systems is one of the outstanding problems in condensed external perturbations. For example, it may be desirable in certain cases to follow the dynamics of atoms/electrons
Calculation of dose to soft tisse from implanted beta sources
Dauffy, Lucile
1998-01-01T23:59:59.000Z
for beta dose calculations are reported in the literature. Monte Carlo codes are very often used but are cumbersome. A Monte Carlo code can be used to model the exact path and energies that a particle assumes as it passes through a medium using random...
Calculating Very Rough Market Share Using the Canadian Business Database
Thompson, Michael
Calculating Very Rough Market Share Using the Canadian Business Database If you cannot find market market share using the company information provided in the Canadian Business Database (CBD), an online - it should be considered a last resort for this information. STEP 1: ACCESS THE CANADIAN BUSINESS DATABASE 1a
Semiclassical calculation of an induced decay of false vacuum
A. Monin; M. B. Voloshin
2010-04-12T23:59:59.000Z
We consider a model where a scalar field develops a metastable vacuum state and weakly interacts with another scalar field. In this situation we find the probability of decay of the false vacuum stimulated by the presence and collisions of particles of the second field. The discussed calculation is an illustration of the recently suggested thermal approach to treatment of induced semiclassical processes.
CALCULATING THE CARBON FOOTPRINT SUPPLY CHAIN FOR THE
Su, Xiao
CALCULATING THE CARBON FOOTPRINT SUPPLY CHAIN FOR THE SEMICONDUCTOR INDUSTRY A LEARNING TOOL By a complete supply chain #12;Carbon Footprint Supply Chain Carbon Trust defines carbon footprint of a supply chain as follows: "The carbon footprint of a product is the carbon dioxide emitted across the supply
SEMIEMPIRICAL MOLECULAR ORBITAL CALCULATIONS OF BAND GAPS OF CONJUGATED POLYMERS
Goddard III, William A.
SEMIEMPIRICAL MOLECULAR ORBITAL CALCULATIONS OF BAND GAPS OF CONJUGATED POLYMERS Tahir Cagin Research and Development Center, Materials Labarotory, Polymer Branch, Wright Patterson AFB, Ohio 45433 geometries and energy band gaps of conjugated polymers. In this study, we used a modified version of semi
Quantum Monte Carlo calculations of symmetric nuclear matter
Stefano Gandolfi; Francesco Pederiva; Stefano Fantoni; Kevin E. Schmidt
2007-04-13T23:59:59.000Z
We present an accurate numerical study of the equation of state of nuclear matter based on realistic nucleon--nucleon interactions by means of Auxiliary Field Diffusion Monte Carlo (AFDMC) calculations. The AFDMC method samples the spin and isospin degrees of freedom allowing for quantum simulations of large nucleonic systems and can provide quantitative understanding of problems in nuclear structure and astrophysics.
Calculated Phonon Spectra of Plutonium at High Temperatures
Savrasov, Sergej Y.
Calculated Phonon Spectra of Plutonium at High Temperatures X. Dai,1 S. Y. Savrasov,2 * G. Kotliar dynamical proper- ties of plutonium using an electronic structure method, which incorporates correlation anharmonic and can be stabilized at high temperatures by its phonon entropy. Plutonium (Pu) is a material
Theoretical calculations and vibrational potential energy surface of 4-silaspiro(3,3)heptane
Ocola, Esther J.; Medders, Cross; Laane, Jaan, E-mail: laane@mail.chem.tamu.edu [Department of Chemistry, Texas A and M University, College Station, Texas 77843-3255 (United States)] [Department of Chemistry, Texas A and M University, College Station, Texas 77843-3255 (United States); Meinander, Niklas [Department of Military Technology, Finnish National Defence University, P.O. Box 7, 00861 Helsinki (Finland)] [Department of Military Technology, Finnish National Defence University, P.O. Box 7, 00861 Helsinki (Finland)
2014-04-28T23:59:59.000Z
Theoretical computations have been carried out on 4-silaspiro(3,3)heptane (SSH) in order to calculate its molecular structure and conformational energies. The molecule has two puckered four-membered rings with dihedral angles of 34.2° and a tilt angle of 9.4° between the two rings. Energy calculations were carried out for different conformations of SSH. These results allowed the generation of a two-dimensional ring-puckering potential energy surface (PES) of the form V = a(x{sub 1}{sup 4} + x{sub 2}{sup 4}) – b(x{sub 1}{sup 2} + x{sub 2}{sup 2}) + cx{sub 1}{sup 2}x{sub 2}{sup 2}, where x{sub 1} and x{sub 2} are the ring-puckering coordinates for the two rings. The presence of sufficiently high potential energy barriers prevents the molecule from undergoing pseudorotation. The quantum states, wave functions, and predicted spectra resulting from the PESs were calculated.
Study of cosmic ray interaction model based on atmospheric muons for the neutrino flux calculation
Sanuki, T.; Honda, M.; Kajita, T.; Kasahara, K.; Midorikawa, S. [International Center for Elementary Particle Physics, University of Tokyo, 7-3-1 Hongo, Bunkyo-ku, Tokyo 113-0033 (Japan); Institute for Cosmic Ray Research, University of Tokyo, 5-1-5 Kashiwa-no-ha, Kashiwa, Chiba 277-8582 (Japan); Shibaura Institute of Technology, 307 Fukasaku, Minuma-ku, Saitama 337-8570 (Japan); Faculty of Software and Information Technology, Aomori University, 2-3-1 Kobata, Aomori, Aomori 030-0943 (Japan)
2007-02-15T23:59:59.000Z
We have studied the hadronic interaction for the calculation of the atmospheric neutrino flux by summarizing the accurately measured atmospheric muon flux data and comparing with simulations. We find the atmospheric muon and neutrino fluxes respond to errors in the {pi}-production of the hadronic interaction similarly, and compare the atmospheric muon flux calculated using the HKKM04 [M. Honda, T. Kajita, K. Kasahara, and S. Midorikawa, Phys. Rev. D 70, 043008 (2004).] code with experimental measurements. The {mu}{sup +}+{mu}{sup -} data show good agreement in the 1{approx}30 GeV/c range, but a large disagreement above 30 GeV/c. The {mu}{sup +}/{mu}{sup -} ratio shows sizable differences at lower and higher momenta for opposite directions. As the disagreements are considered to be due to assumptions in the hadronic interaction model, we try to improve it phenomenologically based on the quark parton model. The improved interaction model reproduces the observed muon flux data well. The calculation of the atmospheric neutrino flux will be reported in the following paper [M. Honda et al., Phys. Rev. D 75, 043006 (2007).].
Three dimensional neutronics calculation comparison study for a fusion breeder with large channels
Huang, J.H.; Xie, Z.Y.; You, C.L. [Southwestern Inst. of Physics, Chengdu (China)] [and others
1994-12-31T23:59:59.000Z
A tokamak reactor is characterized by a toroidal geometry with large ports and channels. The three dimensional calculation seems necessary for the prediction of the neutronics parameters of the calculation. People have been attempting to simulate the configuration by one dimensional model. Assuming that the neutronics parameters such as tritium breeding ratio depends almost only on the primary 14 MeV neutron number entering the blanket, the following approximate scheme was proposed: {Alpha} = {Sigma}W{sub i}{sm_bullet}{Alpha}{sub i}, where {Alpha} represents the total value of a parameter; {Alpha}{sub i} is a partial value contributed from the i`th part of the blanket and is calculated by a 1-D cylindrical model; W{sub i} is the fusion number entering the i`th part of the blanket through the first wall. This scheme seems reasonable for a pure fusion reactor with similar inboard and outboard blankets, since neutron flux angular distribution is strongly forward and the mutual influence between similar blankets is weak. A study on influence between inboard and outboard blankets showed a rather strong influence between blankets in a fusion breeder, where the partial blankets are quite different in neutronics characteristics. The explanation is that the neutron source from fission and n,2n reactions in the outboard blanket causes considerable neutron leakage through the inner surface when it faces an {open_quote}inferior{close_quote} inboard blanket.
Linear calculations of edge current driven kink modes with BOUT++ code
Li, G. Q., E-mail: ligq@ipp.ac.cn; Xia, T. Y. [Institute of Plasma Physics, CAS, Hefei, Anhui 230031 (China); Lawrence Livermore National Laboratory, Livermore, California 94550 (United States); Xu, X. Q. [Lawrence Livermore National Laboratory, Livermore, California 94550 (United States); Snyder, P. B.; Turnbull, A. D. [General Atomics, San Diego, California 92186 (United States); Ma, C. H.; Xi, P. W. [Lawrence Livermore National Laboratory, Livermore, California 94550 (United States); FSC, School of Physics, Peking University, Beijing 100871 (China)
2014-10-15T23:59:59.000Z
This work extends previous BOUT++ work to systematically study the impact of edge current density on edge localized modes, and to benchmark with the GATO and ELITE codes. Using the CORSICA code, a set of equilibria was generated with different edge current densities by keeping total current and pressure profile fixed. Based on these equilibria, the effects of the edge current density on the MHD instabilities were studied with the 3-field BOUT++ code. For the linear calculations, with increasing edge current density, the dominant modes are changed from intermediate-n and high-n ballooning modes to low-n kink modes, and the linear growth rate becomes smaller. The edge current provides stabilizing effects on ballooning modes due to the increase of local shear at the outer mid-plane with the edge current. For edge kink modes, however, the edge current does not always provide a destabilizing effect; with increasing edge current, the linear growth rate first increases, and then decreases. In benchmark calculations for BOUT++ against the linear results with the GATO and ELITE codes, the vacuum model has important effects on the edge kink mode calculations. By setting a realistic density profile and Spitzer resistivity profile in the vacuum region, the resistivity was found to have a destabilizing effect on both the kink mode and on the ballooning mode. With diamagnetic effects included, the intermediate-n and high-n ballooning modes can be totally stabilized for finite edge current density.
Weather data for simplified energy calculation methods. Volume IV. United States: WYEC data
Olsen, A.R.; Moreno, S.; Deringer, J.; Watson, C.R.
1984-08-01T23:59:59.000Z
The objective of this report is to provide a source of weather data for direct use with a number of simplified energy calculation methods available today. Complete weather data for a number of cities in the United States are provided for use in the following methods: degree hour, modified degree hour, bin, modified bin, and variable degree day. This report contains sets of weather data for 23 cities using Weather Year for Energy Calculations (WYEC) source weather data. Considerable overlap is present in cities (21) covered by both the TRY and WYEC data. The weather data at each city has been summarized in a number of ways to provide differing levels of detail necessary for alternative simplified energy calculation methods. Weather variables summarized include dry bulb and wet bulb temperature, percent relative humidity, humidity ratio, wind speed, percent possible sunshine, percent diffuse solar radiation, total solar radiation on horizontal and vertical surfaces, and solar heat gain through standard DSA glass. Monthly and annual summaries, in some cases by time of day, are available. These summaries are produced in a series of nine computer generated tables.
Border flow rights and Contracts for differences of differences
Baldick, Ross
marginal price for energy that it delivers to the rest of the system and pays the locational marginal price analogously to "contracts for differences" (CFDs) that are used to hedge locational marginal price variation implementation of the border flow rights model, the owner of a transmission line or lines is paid the locational
Borodkin, P.G.; Borodkin, G.I.; Khrennikov, N.N. [Scientific and Engineering Centre for Nuclear and Radiation Safety SEC NRS, Malaya Krasnoselskaya ul., 2/8, Bld. 5, 107140 Moscow (Russian Federation); Konheiser, J. [Helmholz Zentrum Dresden-Rossendorf HZDR, Postfach 510119, D-01314 Dresden (Germany)
2011-07-01T23:59:59.000Z
This paper deals with calculated and semi-analytical evaluations of VVER-1000 reactor core neutron source distributions and their influence on measurements and calculations of the integral through-vessel neutron leakage. Neutron activation measurements analyzed in the paper were carried out in an ex-vessel air cavity at different nuclear power plant units with VVER-1000 during different fuel cycles. The time-integrated neutron source distributions used for DORT calculations were prepared via two different approaches based on (a) calculated fuel burnup (standard routine procedure) and (b) in-core measurements by means of self-powered detectors (SPDs) and thermocouples (TCs) (new approach). Considering that fuel burnup distributions in operating VVER may be evaluated now by the use of analytical methods (calculations) only, it is necessary to develop new approaches for the testing and correction of calculated evaluations of a neutron source. The results presented in this paper allow one to consider the reverse task of the alternative estimation of fuel burnup distributions. The proposed approach is based on the adjustment (fitting) of time-integrated neutron source distributions, and thus fuel burnup patterns, in some part of the reactor core, taking into account neutron leakage measurements, neutron-physical calculations, and in-core SPD and TC measurement data. (authors)
Mueller, S; Dunn, JB; Wang, M (Energy Systems); (Univ. of Illinois at Chicago)
2012-06-07T23:59:59.000Z
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.
Stochastic Boundary, Diffusion, Emittance Growth and Lifetime calculation for the RHIC e-lens
Abreu,N.P.; Fischer, W.; Luo, Y.; Robert-Demolaize, G.
2009-01-20T23:59:59.000Z
To compensate the large tune shift and tune spread generated by the head-on beam-beam interactions in polarized proton operation in the Relativistic Heavy Ion Collider (RHIC), a low energy electron beam with proper Gaussian transverse profiles was proposed to collide head-on with the proton beam. In this article, using a modified version of SixTrack [1], we investigate stability of the single particle in the presence of head-on beam-beam compensation. The Lyapunov exponent and action diffusion are calculated and compared between the cases without and with beam-beam compensation for two different working points and various bunch intensities. Using the action diffusion results the emittance growth rate and lifetime of the proton beam is also estimated for the different scenarios.
Bandgap calculations and trends of organometal halide perovskites
Castelli, Ivano E., E-mail: ivca@fysik.dtu.dk; Thygesen, Kristian S.; Jacobsen, Karsten W. [Center for Atomic-scale Materials Design (CAMD), Department of Physics, Technical University of Denmark, DK 2800 Kgs. Lyngby (Denmark); García-Lastra, Juan María [Center for Atomic-scale Materials Design (CAMD), Department of Physics, Technical University of Denmark, DK 2800 Kgs. Lyngby (Denmark); Department of Energy Conversion and Storage, Technical University of Denmark, DK 4000 Roskilde (Denmark)
2014-08-01T23:59:59.000Z
Energy production from the Sun requires a stable efficient light absorber. Promising candidates in this respect are organometal perovskites (ABX{sub 3}), which have been intensely investigated during the last years. Here, we have performed electronic structure calculations of 240 perovskites composed of Cs, CH{sub 3}NH{sub 3}, and HC(NH{sub 2}){sub 2} as A-cation, Sn and Pb as B-ion, and a combination of Cl, Br, and I as anions. The calculated gaps span over a region from 0.5 to 5.0 eV. In addition, the trends over bandgaps have been investigated: the bandgap increases with an increase of the electronegativities of the constituent species, while it reduces with an increase of the lattice constants of the system.
Variational calculations of the HT{sup +} rovibrational energies
Bekbaev, A. K. [Al Farabi Kazakh National University, 050012 Almaty (Kazakhstan); Korobov, V. I. [Joint Institute for Nuclear Research, 141980 Dubna (Russian Federation); Dineykhan, M. [Al Farabi Kazakh National University, 050012 Almaty (Kazakhstan); Joint Institute for Nuclear Research, 141980 Dubna (Russian Federation)
2011-04-15T23:59:59.000Z
In this Brief Report, we use the exponential explicitly correlated variational basis set of the type exp(-{alpha}{sub n}R-{beta}{sub n}r{sub 1}-{gamma}{sub n}r{sub 2}) to calculate systematically the nonrelativistic bound-state energies for the hydrogen molecular ion HT{sup +}. We perform calculations for the states of the total orbital angular momentum L=0 and 1 with the complete set of vibrational quantum numbers v= 0-23, as well as for the states of L= 2-5 and v= 0-5. The E1 dipole transition moments, which are of importance for the planning of spectroscopic laser experiments, have been obtained as well.
Elastic properties of superconducting MAX phases from first principles calculations
I. R. Shein; A. L. Ivanovskii
2010-06-03T23:59:59.000Z
Using first-principles density functional calculations, a systematic study on the elastic properties for all known superconducting MAX phases (Nb2SC, Nb2SnC, Nb2AsC, Nb2InC, Mo2GaC and Ti2InC) was performed. As a result, the optimized lattice parameters, independent elastic constants, indicators of elastic anisotropy and brittle/ductile behavior as well as the so-called machinability indexis were calculated. We derived also bulk and shear moduli, Young's moduli, and Poisson's ratio for ideal polycrystalline MAX aggregates. The results obtained were discussed in comparison with available theoretical and experimental data and elastic parameters for other layered superconductors.
On the calculation of percentile-based bibliometric indicators
Waltman, Ludo
2012-01-01T23:59:59.000Z
A percentile-based bibliometric indicator is an indicator that values publications based on their position within the citation distribution of their field. The most straightforward percentile-based indicator is the proportion of frequently cited publications, for instance the proportion of publications that belong to the top 10% most frequently cited of their field. Recently, more complex percentile-based indicators were proposed. A difficulty in the calculation of percentile-based indicators is caused by the discrete nature of citation distributions combined with the presence of many publications with the same number of citations. We introduce an approach to calculating percentile-based indicators that deals with this difficulty in a more satisfactory way than earlier approaches suggested in the literature. We show in a formal mathematical framework that our approach leads to indicators that do not suffer from biases in favor of or against particular fields of science.
CALOR89 calorimeter simulations, benchmarking, and design calculations
Handler, T. (Tennessee Univ., Knoxville, TN (USA)); Panakkal, J.K.; Proudfoot, J. (Argonne National Lab., IL (USA)); Cremaldi, L.; Moore, B.; Reidy, J.J. (Mississippi Univ., University, MS (USA)); Alsmiller, R.G. Jr.; Fu, P.; Gabriel, T.A. (Oak Ridge National Lab., TN (USA))
1990-01-01T23:59:59.000Z
Results on CALOR89 benchmarking and design calculations utilizing the CALOR89 programs are presented. The benchmarking is done with respect to the ZEUS and DO calorimeters. The design calculations were done for a variety of absorbers (depleted uranium, lead, and iron) of various thickness for a given scintillator thickness and for a fixed absorber thickness using various thickness for the scintillator. These studies indicate that a compensating calorimeter can be built using lead as the absorber, whereas a purely iron calorimeter would be non-compensating. A depleted uranium calorimeter would possibly be unsuitable if used in a large configuration and a high luminosity machine because of the delayed energy release from capture gammas. 11 refs., 5 figs.
SOLGAS refined: A computerized thermodynamic equilibrium calculation tool
Trowbridge, L.D.; Leitnaker, J.M.
1993-11-01T23:59:59.000Z
SOLGAS, an early computer program for calculating equilibrium in a chemical system, has been made more user-friendly, and several{open_quote} bells and whistles{close_quotes} have been added. The necessity to include elemental species has been eliminated. The input of large numbers of starting conditions has been automated. A revised format for entering data simplifies and reduces chances for error. Calculated errors by SOLGAS are flagged, and several programming errors are corrected. Auxiliary programs are available to assemble and partially automate plotting of large amounts of data. Thermodynamic input data can be changed {open_quotes}on line.{close_quote} The program can be operated with or without a co-processor. Copies of the program, suitable for the IBM-PC or compatible with at least 384 bytes of low RAM, are available from the authors.
Mesoscale polycrystal calculations of damage in spallation in metals
Tonks, Davis L [Los Alamos National Laboratory; Bingert, John F [Los Alamos National Laboratory; Livescu, Veronica [Los Alamos National Laboratory; Luo, Shengnian [Los Alamos National Laboratory; Bronkhorst, C A [Los Alamos National Laboratory
2010-01-01T23:59:59.000Z
The goal of this project is to produce a damage model for spallation in metals informed by the polycrystalline grain structure at the mesoscale. Earlier damage models addressed the continuwn macroscale in which these effects were averaged out. In this work we focus on cross sections from recovered samples examined with EBSD (electron backscattered diffraction), which reveal crystal grain orientations and voids. We seek to understand the loading histories of specific sample regions by meshing up the crystal grain structure of these regions and simulating the stress, strain, and damage histories in our hydro code, FLAG. The stresses and strain histories are the fundamental drivers of damage and must be calculated. The calculated final damage structures are compared with those from the recovered samples to validate the simulations.
Calculation of thermal parameters of SiGe microbolometers
Voitsekhovskii, A V; Yuryev, V A; Nesmelov, S N; 10.1007/s11182-008-9015-4
2012-01-01T23:59:59.000Z
The thermal parameters of a SiGe microbolometer were calculated using numerical modeling. The calculated thermal conduction and thermal response time are in good agreement with the values found experimentally and range between 2x10$^-7$ and 7x10$^-8$ W/K and 1.5 and 4.5 ms, respectively. High sensitivity of microbolometer is achieved due to optimization of the thermal response time and thermal conduction by fitting the geometry of supporting heat-removing legs or by selection of a suitable material providing boundary thermal resistance higher than 8x10$^-3$ cm$^2$K/W at the SiGe interface.
Range and modulation dependencies for proton beam dose per monitor unit calculations
Hsi, Wen C.; Schreuder, Andries N.; Moyers, Michael F.; Allgower, Chris E.; Farr, Jonathan B.; Mascia, Anthony E. [Midwest Proton Radiotherapy Institute, Bloomington, Indiana 47408 and University Florida Proton Therapy Institute, Jacksonville, Florida 32206 (United States); ProCure Treatment Centers, Inc., Bloomington, Indiana 47404 (United States); Proton Therapy, Inc., Colton, California 92324 (United States); Midwest Proton Radiotherapy Institute, Bloomington, Indiana 47408 (United States); Midwest Proton Radiotherapy Institute, Bloomington, Indiana 47408 and Westdeutsches Protonentherapiezentrum, Universitaetsklinikum, Hufelandstrasse 55, 45147 Essen (Germany); Midwest Proton Radiotherapy Institute, Bloomington, Indiana 47408 (United States)
2009-02-15T23:59:59.000Z
Calculations of dose per monitor unit (D/MU) are required in addition to measurements to increase patient safety in the clinical practice of proton radiotherapy. As in conventional photon and electron therapy, the D/MU depends on several factors. This study focused on obtaining range and modulation dependence factors used in D/MU calculations for the double scattered proton beam line at the Midwest Proton Radiotherapy Institute. Three dependencies on range and one dependency on modulation were found. A carefully selected set of measurements was performed to discern these individual dependencies. Dependencies on range were due to: (1) the stopping power of the protons passing through the monitor chamber; (2) the reduction of proton fluence due to nuclear interactions within the patient; and (3) the variation of proton fluence passing through the monitor chamber due to different source-to-axis distances (SADs) for different beam ranges. Different SADs are produced by reconfigurations of beamline elements to provide different field sizes and ranges. The SAD effect on the D/MU varies smoothly as the beam range is varied, except at the beam range for which the first scatterers are exchanged and relocated to accommodate low and high beam ranges. A geometry factor was devised to model the SAD variation effect on the D/MU. The measured D/MU variation as a function of range can be predicted within 1% using the three modeled dependencies on range. Investigation of modulated beams showed that an analytical formula can predict the D/MU dependency as a function of modulation to within 1.5%. Special attention must be applied when measuring the D/MU dependence on modulation to avoid interplay between range and SAD effects.
New correlation accurately calculates water solubilities of aromatics
Yaws, C.L.; Bu, L.; Nijhawan, S. (Lamar Univ., Beaumont, TX (United States))
1994-08-29T23:59:59.000Z
A new correlation calculates reliable aromatics solubilities in water down to very low concentrations. The correlation, based on boiling point, can be used for initial engineering studies. The importance of hydrocarbon solubility in water is increasing because of health, safety, and environmental issues. The paper begins with a discussion of the importance of solubility, even at low concentrations. The new correlation is described, aromatics are compared with paraffins, and the new correlation is compared with the API correlation.
Water coning calculations for vertical and horizontal wells
Yang, Weiping
1990-01-01T23:59:59.000Z
recovery of several wells coning water. Since their type curves are specific for the data they investigated, it can not serve as a general method of coning evaluation. Addington'2 developed a set of gas coning correlations for 3-D coarse grid... for predicting (1) critical coning rate, (2) breakthrough time, and (3) WOR after breakthrough in both vertical and horizontal wells. Two hand calculation methods had been developed in this study. Either of them applies to both vertical and horizontal wells...
94 home power 95 / june & july 2003 Calculations
Johnson, Eric E.
94 home power 95 / june & july 2003 Code Calculations for an Off-Grid PV System The walls are up and the PV system is being assembled for the off-grid home described in Code Corner in HP94. This article National Laboratories Judy LaPointe's home is on its way to becoming a finished, off-grid home. #12;95www
An alternative method for calculating the energy of gravitational waves
Miroslav Sukenik; Jozef Sima
1999-09-21T23:59:59.000Z
In the expansive nondecelerative universe model, creation of matter occurs due to which the Vaidya metrics is applied. This fact allows for localizing gravitational energy and calculating the energy of gravitational waves using an approach alternative to the well established procedure based on quadrupole formula. Rationalization of the gradual increase in entropy of the Universe using relation describing the total curvature of space-time is given too.
Validation of Criticality Safety Calculations with SCALE 6.2
Marshall, William BJ J [ORNL] [ORNL; Wiarda, Dorothea [ORNL] [ORNL; Celik, Cihangir [ORNL] [ORNL; Rearden, Bradley T [ORNL] [ORNL
2013-01-01T23:59:59.000Z
SCALE 6.2 provides numerous updates in nuclear data, nuclear data processing, and computational tools utilized in the criticality safety calculational sequences relative to SCALE 6.1. A new 252-group ENDF/B-VII.0 multigroup neutron library, improved ENDF/B-VII.0 continuous energy data, as well as the previously deployed 238-group ENDF/B-VII.0 neutron library are included in SCALE 6.2 for criticality safety analysis. The performance of all three libraries for keff calculations is examined with a broad sampling of critical experiment models covering a range of fuels and moderators. Critical experiments from the International Handbook of Evaluated Criticality Safety Benchmark Experiments (IHECSBE) that are available in the SCALE Verified, Archived Library of Inputs and Data (VALID) are used in this validation effort. Over 300 cases are used in the validation of KENO V.a, and a more limited set of approximately 50 configurations are used for KENO-VI validation. Additionally, some KENO V.a cases are converted to KENO-VI models so that an equivalent set of experiments can be used to validate both codes. For continuous-energy calculations, SCALE 6.2 provides improved performance relative to SCALE 6.1 in most areas with notable improvements in fuel pin lattice cases, particularly those with mixed oxide fuel. Multigroup calculations with the 252-group library also demonstrate improved performance for fuel lattices, uranium (high and intermediate enrichment) and plutonium metal experiments, and plutonium solution systems. Overall, SCALE 6.2 provides equivalent or smaller biases than SCALE 6.1, and the two versions of KENO provide similar results on the same suite of problems.
Cluster-model calculations of exotic decays from heavy nuclei
Buck, B.; Merchant, A.C.
1989-05-01T23:59:59.000Z
A cluster model employing a local, effective cluster-core potential is used to investigate exotic decay from heavy nuclei as a quantum tunneling phenomenon within a semiclassical approximation. Excellent agreement with all reported experimental measurements of the decay widths for /sup 14/C and /sup 24/Ne emission is obtained. As an added bonus, the width for alpha particle emission from /sup 212/Po is also calculated in good agreement with experiment.
Statewide Air Emissions Calculations from Energy Efficiency, Wind and Renewables
Haberl, J.; Yazdani, B.; Culp, C.
2008-01-01T23:59:59.000Z
AND RENEWABLES May 2008 Energy Systems Laboratory p. 2 Electricity Production from Wind Farms (2002-2007) ? Installed capacity of wind turbines was 3,026 MW (March 2007). ? Announced new project capacity is 3,125 MW by 2010. ? Lowest electricity period... Energy Systems Laboratory p. 1 Jeff Haberl, Bahman Yazdani, Charles Culp Energy Systems Laboratory Texas Engineering Experiment Station Texas A&M University System STATEWIDE AIR EMISSIONS CALCULATIONS FROM ENERGY EFFICIENCY, WIND...
Quantum Monte Carlo calculations of neutron-alpha scattering
Kenneth M. Nollett; Steven C. Pieper; R. B. Wiringa; J. Carlson; G. M. Hale
2006-12-09T23:59:59.000Z
We describe a new method to treat low-energy scattering problems in few-nucleon systems, and we apply it to the five-body case of neutron-alpha scattering. The method allows precise calculations of low-lying resonances and their widths. We find that a good three-nucleon interaction is crucial to obtain an accurate description of neutron-alpha scattering.
Quantum Monte Carlo Calculations of Symmetric Nuclear Matter
Gandolfi, Stefano [Dipartimento di Fisica and INFN, University of Trento, via Sommarive 14, I-38050 Povo, Trento (Italy); Pederiva, Francesco [Dipartimento di Fisica and INFN, University of Trento, via Sommarive 14, I-38050 Povo, Trento (Italy); CNR-DEMOCRITOS National Supercomputing Center, Trieste (Italy); Fantoni, Stefano [Scuola Internazionale Superiore di Studi Avanzati and INFN via Beirut 2/4, 34014 Trieste (Italy); CNR-DEMOCRITOS National Supercomputing Center, Trieste (Italy); Schmidt, Kevin E. [Department of Physics, Arizona State University, Tempe, Arizona (United States)
2007-03-09T23:59:59.000Z
We present an accurate numerical study of the equation of state of nuclear matter based on realistic nucleon-nucleon interactions by means of auxiliary field diffusion Monte Carlo (AFDMC) calculations. The AFDMC method samples the spin and isospin degrees of freedom allowing for quantum simulations of large nucleonic systems and represents an important step forward towards a quantitative understanding of problems in nuclear structure and astrophysics.
NAC-1 cask dose rate calculations for LWR spent fuel
CARLSON, A.B.
1999-02-24T23:59:59.000Z
A Nuclear Assurance Corporation nuclear fuel transport cask, NAC-1, is being considered as a transport and storage option for spent nuclear fuel located in the B-Cell of the 324 Building. The loaded casks will be shipped to the 200 East Area Interim Storage Area for dry interim storage. Several calculations were performed to assess the photon and neutron dose rates. This report describes the analytical methods, models, and results of this investigation.
Duan, Yuhua
2012-11-02T23:59:59.000Z
Since current technologies for capturing CO{sub 2} to fight global climate change are still too energy intensive, there is a critical need for development of new materials that can capture CO{sub 2} reversibly with acceptable energy costs. Accordingly, solid sorbents have been proposed to be used for CO{sub 2} capture applications through a reversible chemical transformation. By combining thermodynamic database mining with first principles density functional theory and phonon lattice dynamics calculations, a theoretical screening methodology to identify the most promising CO{sub 2} sorbent candidates from the vast array of possible solid materials has been proposed and validated. The calculated thermodynamic properties of different classes of solid materials versus temperature and pressure changes were further used to evaluate the equilibrium properties for the CO{sub 2} adsorption/desorption cycles. According to the requirements imposed by the pre- and post- combustion technologies and based on our calculated thermodynamic properties for the CO{sub 2} capture reactions by the solids of interest, we were able to screen only those solid materials for which lower capture energy costs are expected at the desired pressure and temperature conditions. Only those selected CO{sub 2} sorbent candidates were further considered for experimental validations. The ab initio thermodynamic technique has the advantage of identifying thermodynamic properties of CO{sub 2} capture reactions without any experimental input beyond crystallographic structural information of the solid phases involved. Such methodology not only can be used to search for good candidates from existing database of solid materials, but also can provide some guidelines for synthesis new materials. In this presentation, we first introduce our screening methodology and the results on a testing set of solids with known thermodynamic properties to validate our methodology. Then, by applying our computational method to several different kinds of solid systems, we demonstrate that our methodology can predict the useful information to help developing CO{sub 2} capture Technologies.
Ab initio calculation of the electronic absorption spectrum of liquid water
Martiniano, Hugo F. M. C.; Galamba, Nuno [Grupo de Física Matemática da Universidade de Lisboa, Av. Professor Gama Pinto 2, 1649-003 Lisboa (Portugal)] [Grupo de Física Matemática da Universidade de Lisboa, Av. Professor Gama Pinto 2, 1649-003 Lisboa (Portugal); Cabral, Benedito J. Costa, E-mail: ben@cii.fc.ul.pt [Grupo de Física Matemática da Universidade de Lisboa, Av. Professor Gama Pinto 2, 1649-003 Lisboa (Portugal) [Grupo de Física Matemática da Universidade de Lisboa, Av. Professor Gama Pinto 2, 1649-003 Lisboa (Portugal); Departamento de Química e Bioquímica, Faculdade de Ciências, Universidade de Lisboa, 1749-016 Lisboa (Portugal); Instituto de Física da Universidade de São Paulo, CP 66318, 05314-970 São Paulo, SP (Brazil)
2014-04-28T23:59:59.000Z
The electronic absorption spectrum of liquid water was investigated by coupling a one-body energy decomposition scheme to configurations generated by classical and Born-Oppenheimer Molecular Dynamics (BOMD). A Frenkel exciton Hamiltonian formalism was adopted and the excitation energies in the liquid phase were calculated with the equation of motion coupled cluster with single and double excitations method. Molecular dynamics configurations were generated by different approaches. Classical MD were carried out with the TIP4P-Ew and AMOEBA force fields. The BLYP and BLYP-D3 exchange-correlation functionals were used in BOMD. Theoretical and experimental results for the electronic absorption spectrum of liquid water are in good agreement. Emphasis is placed on the relationship between the structure of liquid water predicted by the different models and the electronic absorption spectrum. The theoretical gas to liquid phase blue-shift of the peak positions of the electronic absorption spectrum is in good agreement with experiment. The overall shift is determined by a competition between the O–H stretching of the water monomer in liquid water that leads to a red-shift and polarization effects that induce a blue-shift. The results illustrate the importance of coupling many-body energy decomposition schemes to molecular dynamics configurations to carry out ab initio calculations of the electronic properties in liquid phase.
Spatial homogenization of thermal feedback regions in Monte Carlo reactor calculations
Hanna, B. R.; Gill, D. F.; Griesheimer, D. P. [Bertis Atomic Power Laboratory, Bechtel Marine Propulsion Corporation, P.O. Box 79, West Mifflin, PA 15122 (United States)
2012-07-01T23:59:59.000Z
An integrated thermal-hydraulic feedback module has previously been developed for the Monte Carlo transport solver, MC21. The module incorporates a flexible input format that allows the user to describe heat transfer and coolant flow paths within the geometric model at any level of spatial detail desired. The effect that the varying levels of spatial homogenization of thermal regions has on the accuracy of the Monte Carlo simulations is examined in this study. Six thermal feedback mappings are constructed from the same geometric model of the Calvert Cliffs core. The spatial homogenization of the thermal regions is varied, giving each scheme a different level of detail, and the adequacy of the spatial homogenization is determined based on the eigenvalue produced by each Monte Carlo calculation. The purpose of these numerical experiments is to determine the level of detail necessarily to accurately capture the thermal feedback effect on reactivity. Several different core models are considered: axial-flow only, axial and lateral flow, asymmetry due to control rod insertion, and fuel heating (temperature -dependent cross sections). The thermal results generated by the MC21 thermal feedback module are consistent with expectations. Based upon the numerical experiments conducted it is concluded that the amount of spatial detail necessary to accurately capture the feedback effect on reactivity is relatively small. Homogenization at the assembly level for the Calvert Cliffs PWR model results in a similar power defect to that calculated with individual pin-cells modeled as explicit thermal regions. (authors)
Exact-to-precision generalized perturbation for neutron transport calculation
Wang, C.; Abdel-Khalik, H. S. [North Carolina State University, 911 Oval Dr., Centennial Campus, Raleigh, NC 27606 (United States)
2013-07-01T23:59:59.000Z
This manuscript extends the exact-to-precision generalized perturbation theory (E{sub P}GPT), introduced previously, to neutron transport calculation whereby previous developments focused on neutron diffusion calculation only. The E{sub P}GPT collectively denotes new developments in generalized perturbation theory (GPT) that place premium on computational efficiency and defendable accuracy in order to render GPT a standard analysis tool in routine design and safety reactor calculations. EPGPT constructs a surrogate model with quantifiable accuracy which can replace the original neutron transport model for subsequent engineering analysis, e.g. functionalization of the homogenized few-group cross sections in terms of various core conditions, sensitivity analysis and uncertainty quantification. This is achieved by reducing the effective dimensionality of the state variable (i.e. neutron angular flux) by projection onto an active subspace. Confining the state variations to the active subspace allows one to construct a small number of what is referred to as the 'active' responses which are solely dependent on the physics model rather than on the responses of interest, the number of input parameters, or the number of points in the state phase space. (authors)
Atmospheric neutrino flux calculation using the NRLMSISE00 atmospheric model
Honda, M; Kajita, T; Kasahara, K; Midorikawa, S
2015-01-01T23:59:59.000Z
In this paper, we extend the calculation of the atmospheric neutrino flux~\\cite{hkkm2004,hkkms2006,hkkm2011} to the sites in polar and tropical regions. In our earliest full 3D-calculation~\\cite{hkkm2004}, we used DPMJET-III~\\cite{dpm} for the hadronic interaction model above 5~GeV, and NUCRIN~\\cite{nucrin} below 5~GeV. We modified DPMJET-III as in Ref.~\\cite{hkkms2006} to reproduce the experimental muon spectra better, mainly using the data observed by BESS group~\\cite{BESSTeVpHemu}. In a recent work~\\cite{hkkm2011}, we introduced JAM interaction model for the low energy hadronic interactions. JAM is a nuclear interaction model developed with PHITS (Particle and Heavy-Ion Transport code System)~\\cite{phits}. In Ref.~\\cite{hkkm2011}, we could reproduce the observed muon flux at the low energies at balloon altitude with DPMJET-III above 32 GeV and JAM below that better than the combination of DPMJET-III above 5~GeV and NUCRIN below that. Besides the interaction model, we have also improved the calculation sche...
A general higher-order remap algorithm for ALE calculations
Chiravalle, Vincent P [Los Alamos National Laboratory
2011-01-05T23:59:59.000Z
A numerical technique for solving the equations of fluid dynamics with arbitrary mesh motion is presented. The three phases of the Arbitrary Lagrangian Eulerian (ALE) methodology are outlined: the Lagrangian phase, grid relaxation phase and remap phase. The Lagrangian phase follows a well known approach from the HEMP code; in addition the strain rate andflow divergence are calculated in a consistent manner according to Margolin. A donor cell method from the SALE code forms the basis of the remap step, but unlike SALE a higher order correction based on monotone gradients is also added to the remap. Four test problems were explored to evaluate the fidelity of these numerical techniques, as implemented in a simple test code, written in the C programming language, called Cercion. Novel cell-centered data structures are used in Cercion to reduce the complexity of the programming and maximize the efficiency of memory usage. The locations of the shock and contact discontinuity in the Riemann shock tube problem are well captured. Cercion demonstrates a high degree of symmetry when calculating the Sedov blast wave solution, with a peak density at the shock front that is similar to the value determined by the RAGE code. For a flyer plate test problem both Cercion and FLAG give virtually the same velocity temporal profile at the target-vacuum interface. When calculating a cylindrical implosion of a steel shell, Cercion and FLAG agree well and the Cercion results are insensitive to the use of ALE.
WIPP Benchmark calculations with the large strain SPECTROM codes
Callahan, G.D.; DeVries, K.L. [RE/SPEC, Inc., Rapid City, SD (United States)
1995-08-01T23:59:59.000Z
This report provides calculational results from the updated Lagrangian structural finite-element programs SPECTROM-32 and SPECTROM-333 for the purpose of qualifying these codes to perform analyses of structural situations in the Waste Isolation Pilot Plant (WIPP). Results are presented for the Second WIPP Benchmark (Benchmark II) Problems and for a simplified heated room problem used in a parallel design calculation study. The Benchmark II problems consist of an isothermal room problem and a heated room problem. The stratigraphy involves 27 distinct geologic layers including ten clay seams of which four are modeled as frictionless sliding interfaces. The analyses of the Benchmark II problems consider a 10-year simulation period. The evaluation of nine structural codes used in the Benchmark II problems shows that inclusion of finite-strain effects is not as significant as observed for the simplified heated room problem, and a variety of finite-strain and small-strain formulations produced similar results. The simplified heated room problem provides stratigraphic complexity equivalent to the Benchmark II problems but neglects sliding along the clay seams. The simplified heated problem does, however, provide a calculational check case where the small strain-formulation produced room closures about 20 percent greater than those obtained using finite-strain formulations. A discussion is given of each of the solved problems, and the computational results are compared with available published results. In general, the results of the two SPECTROM large strain codes compare favorably with results from other codes used to solve the problems.
New quinternary selenides: Syntheses, characterizations, and electronic structure calculations
Chung, Ming-Yan; Lee, Chi-Shen, E-mail: chishen@mail.nctu.edu.tw
2013-06-01T23:59:59.000Z
Five quinternary selenides, Sr?.??Y?.??Ge?.??Sb?.??Se? (I), Sr?.??La?.??Ge?.??Sb?.??Se? (II), Sr?.??La?.??Sn?.??Bi?.??Se? (III), Ba?.?? La?.?? Sn?.??Sb?.??Se? (IV), and Ba?.?? La?.??Sn?.??Bi?.??Se? (V), were synthesized by solid-state reaction in fused silica tubes. These compounds are isostructural and crystallize in the Sr?GeSb?Se? structural-type, which belongs to the orthorhombic space group Pnma (no. 62). Three structural units, ^{1}_{?}[MSe?], ^{1}_{?}[M?Se??] (M=Tt, Pn) and M´ (M´=groups II and III element), comprise the entire one-dimensional structure, separated by M´. Measurements of electronic resistivity and diffused reflectance suggest that IV and V have semiconducting properties. Electronic structure calculations confirm the site preferences of Sr/La element discovered by crystal structure refinement. - Graphical abstract: Quinternary selenides Ae?.??M?.??Tt?.??Pn?.??Se? (Ae, M, Tt, Pn=Sr/Ba, Y/La, Ge/Sn, Sb/Bi) were synthesized and their site preferences were characterized by single-crystal X-ray diffraction and electronic structure calculation. Highlights: • Five new quinternary selenides were synthesized and characterized. • Structural units, ^{1}_{?}[MSe?] and ^{1}_{?}[M?Se??] (M=Tt, Pn), construct the one-dimensional structure. • Calculations of electronic structure confirm site preference of Sr/La sites.
Application of nuclear models to neutron nuclear cross section calculations
Young, P.G.
1982-01-01T23:59:59.000Z
Nuclear theory is used increasingly to supplement and extend the nuclear data base that is available for applied studies. Areas where theoretical calculations are most important include the determination of neutron cross sections for unstable fission products and transactinide nuclei in fission reactor or nuclear waste calculations and for meeting the extensive dosimetry, activation, and neutronic data needs associated with fusion reactor development, especially for neutron energies above 14 MeV. Considerable progress has been made in the use of nuclear models for data evaluation and, particularly, in the methods used to derive physically meaningful parameters for model calculations. Theoretical studies frequently involve use of spherical and deformed optical models, Hauser-Feshbach statistical theory, preequilibrium theory, direct-reaction theory, and often make use of gamma-ray strength function models and phenomenological (or microscopic) level density prescriptions. The development, application, and limitations of nuclear models for data evaluation are discussed, with emphasis on the 0.1 to 50 MeV energy range. (91 references).
New, Joshua Ryan [ORNL; Levinson, Ronnen [Lawrence Berkeley National Laboratory (LBNL); Huang, Yu (Joe) [White Box Technologies; Sanyal, Jibonananda [ORNL; Miller, William A [ORNL; Mellot, Joe [The Garland Company; Childs, Kenneth W [ORNL; Kriner, Scott [Green Metal Consulting, Inc.
2014-06-01T23:59:59.000Z
The Roof Savings Calculator (RSC) was developed through collaborations among Oak Ridge National Laboratory (ORNL), White Box Technologies, Lawrence Berkeley National Laboratory (LBNL), and the Environmental Protection Agency in the context of a California Energy Commission Public Interest Energy Research project to make cool-color roofing materials a market reality. The RSC website and a simulation engine validated against demonstration homes were developed to replace the liberal DOE Cool Roof Calculator and the conservative EPA Energy Star Roofing Calculator, which reported different roof savings estimates. A preliminary analysis arrived at a tentative explanation for why RSC results differed from previous LBNL studies and provided guidance for future analysis in the comparison of four simulation programs (doe2attic, DOE-2.1E, EnergyPlus, and MicroPas), including heat exchange between the attic surfaces (principally the roof and ceiling) and the resulting heat flows through the ceiling to the building below. The results were consolidated in an ORNL technical report, ORNL/TM-2013/501. This report is an in-depth inter-comparison of four programs with detailed measured data from an experimental facility operated by ORNL in South Carolina in which different segments of the attic had different roof and attic systems.
Chen, Y.; Li, X.; Zhang, Q.; Spitler, J.; Fisher, D.
2006-01-01T23:59:59.000Z
USA lxq9031@yahoo.com.cn Abstract: Conduction transfer functions (CTFs) are widely used to calculate conduction heat transfer in building cooling load and energy calculations. They can conveniently fit into any load and energy calculation...
TheRate: Program for Ab Initio Direct Dynamics Calculations of Thermal and
Truong, Thanh N.
, and the convergence of the rate constants with respect to the number of electronic structure calculations. 1998 John is that such limited potential energy information may be obtained from accurate electronic structure calculations-- --Dynamics Calculations of Thermal and Vibrational
Shi, Zongqian; Wang, Kun; Li, Yao; Shi, Yuanjie; Wu, Jian; Jia, Shenli [State Key Laboratory of Electrical Insulation and Power Equipment, Xi'an Jiaotong University, Shanxi 710049 (China)] [State Key Laboratory of Electrical Insulation and Power Equipment, Xi'an Jiaotong University, Shanxi 710049 (China)
2014-03-15T23:59:59.000Z
The electron chemical potential and ion charge state (average ion charge and ion distribution) are important parameters in calculating plasma conductivity in electrical explosion of metal wire. In this paper, the calculating method of electron chemical potential and ion charge state is discussed at first. For the calculation of electron chemical potential, the ideal free electron gas model and Thomas-Fermi model are compared and analyzed in terms of the coupling constant of plasma. The Thomas-Fermi ionization model, which is used to calculate ion charge state, is compared with the method based on Saha equation. Furthermore, the influence of electron degenerated energy levels and ion excited states in Saha equation on the ion charge state is also analyzed. Then the influence of different calculating methods of electron chemical potential and ion charge state on plasma conductivity is discussed by applying them in the Lee-More conductivity model.
Kostal, M.; Juricek, V.; Rypar, V.; Svadlenkova, M. [Research Center Rez Ltd., 250 68 Husinec-Rez 130 (Czech Republic); Cvachovec, F. [Univ. of Defence, Kounicova 65, 662 10 Brno (Czech Republic)
2011-07-01T23:59:59.000Z
The power density distribution in a reactor has significant influence on core structures and pressure vessel mechanical resistance, as well as on the physical characteristics of nuclear fuel. This quantity also has an effect on the leakage neutron and photon field. This issue has become of increasing importance, as it touches on actual questions of the VVER nuclear power plant life time extension. This paper shows the comparison of calculated and experimentally determined pin by pin power distributions. The calculation has been performed with deterministic and Monte Carlo approaches. This quantity is accompanied by the neutron and photon flux density calculation and measurements at different points of the light water zero-power (LR-0) research reactor mock-up core, reactor built-in component (core barrel), and reactor pressure vessel and model. The effect of the different data libraries used for calculation is discussed. (authors)
Methods of calculating the post-closure performance of high-level waste repositories
Ross, B. (ed.)
1989-02-01T23:59:59.000Z
This report is intended as an overview of post-closure performance assessment methods for high-level radioactive waste repositories and is designed to give the reader a broad sense of the state of the art of this technology. As described here, ''the state of the art'' includes only what has been reported in report, journal, and conference proceedings literature through August 1987. There is a very large literature on the performance of high-level waste repositories. In order to make a review of this breadth manageable, its scope must be carefully defined. The essential principle followed is that only methods of calculating the long-term performance of waste repositories are described. The report is organized to reflect, in a generalized way, the logical order to steps that would be taken in a typical performance assessment. Chapter 2 describes ways of identifying scenarios and estimating their probabilities. Chapter 3 presents models used to determine the physical and chemical environment of a repository, including models of heat transfer, radiation, geochemistry, rock mechanics, brine migration, radiation effects on chemistry, and coupled processes. The next two chapters address the performance of specific barriers to release of radioactivity. Chapter 4 treats engineered barriers, including containers, waste forms, backfills around waste packages, shaft and borehole seals, and repository design features. Chapter 5 discusses natural barriers, including ground water systems and stability of salt formations. The final chapters address optics of general applicability to performance assessment models. Methods of sensitivity and uncertainty analysis are described in Chapter 6, and natural analogues of repositories are treated in Chapter 7. 473 refs., 19 figs., 2 tabs.
J. W. Sterbentz
1999-08-01T23:59:59.000Z
Six uranium isotopes and fourteen fission product isotopes were calculated on a mass basis at end-of-life (EOL) conditions for three fuel rods from different Light Water Breeder Reactor (LWBR) measurements. The three fuel rods evaluated here were taken from an LWBR seed module, a standard blanket module, and a reflector (Type IV) module. The calculated results were derived using a depletion methodology previously employed to evaluate many of the radionuclide inventories for spent nuclear fuels at the Idaho National Engineering and Environmental Laboratory. The primary goal of the calculational task was to further support the validation of this particular calculational methodology and its application to diverse reactor types and fuels. Result comparisons between the calculated and measured mass concentrations in the three rods indicate good agreement for the three major uranium isotopes (U-233, U-234, U-235) with differences of less than 20%. For the seed and standard blanket rod, the U-233 and U-234 differences were within 5% of the measured values (these two isotopes alone represent greater than 97% of the EOL total uranium mass). For the major krypton and xenon fission product isotopes, differences of less than 20% and less than 30% were observed, respectively. In general, good agreement was obtained for nearly all the measured isotopes. For these isotopes exhibiting significant differences, possible explanations are discussed in terms of measurement uncertainty, complex transmutations, etc.
Pyranometers and Reference Cells, What's the Difference?: Preprint
Meydbray, J.; Emery, K.; Kurtz, S.
2012-03-01T23:59:59.000Z
As the photovoltaic industry has grown exponentially in the past decade, large photovoltaic (PV) fields have become more common. The investors for these projects calculate the expected return on investment based on expected electricity generation and adjust the interest rates and other financial terms according to the perceived risk. These calculations usually assume worst case according to the listed warranty and any uncertainty in the measurement is translated directly into a reduced predicted performance. Because a 1% difference in predicted output could represent a large fraction of the expected return on investment, a small reduction in uncertainty translates into a much larger value to the entity making investment decisions. To reduce perceived risk in large-scale solar investments power plant performance (or production) guarantees have become increasingly common. This two part article explores some subtleties of accurately measuring PV efficiency in the field.
Cardan, R [UAB University of Alabama, Birmingham, Birmingham, AL (United States); Faught, A [MD Anderson Cancer Center, Houston, TX (United States); Huang, M; Benhabib, S [University of Alabama at Birmingham, Birmingham, AL (United States); Brezovich, I; Popple, R [University of Alabama Birmingham, Birmingham, AL (United States); Followill, D [UT MD Anderson Cancer Center, Houston, TX (United States)
2014-06-01T23:59:59.000Z
Purpose: Determine the dose calculation accuracy of a preconfigured Mobius server for use in secondary checks of a treatment planning system. Methods: 10 plans were created for irradiation on two of the IROC (formerly RPC) accreditation phantoms: 4 for the head and neck phantom and 6 for the lung phantom. The plans each were created using one of four different photon energies (6FFF, 10 FFF, 6X, and 15X) and were varied in treatment type including VMAT, step and shoot IMRT, dynamic MLC IMRT (DMLC), and conformal RT (CRT). The TLDs in the phantoms were contoured, and each plan was sent for calculation to Mobius software (Mobius Medical Systems, Houston, TX) with a default configuration. Each plan was then irradiated on the planned phantom 3 times to create an average reading across 56 TLDs. These readings were then compared against the corresponding Mobius calculation at each TLD location. Results: The mean difference (MD) normalized to the plan prescription dose between each TLD and Mobius calculation for all measurements was 0.5 ± 3.3%, with a maximum difference of 8.4%. The MD was 0.6 ± 3.8%, ? 2.0 ± 1.9%, 1.7 ± 3.7%, and 1.9 ± 1.2% across the 6FFF, 10FFF, 6X and 15X energies respectively. The MD was ?1.2 ± 2.3% for lung plans and 1.8 ± 3.5% for head/neck plans. Across treatment types, the MD ranged from ? 1.8 ± 1.7% for CRT to 4.3 ± 2.4 % for DMLC. Conclusion: Out of the box and preconfigured, Mobius provides accurate dose calculations with respect to beam energy, treatment type, and treatment site.
Color Printer Characterization Adjustment for Different
Sharma, Gaurav
is often implemented as a 3D look-up table that maps from a device independent color space (e.g. CIELAB by printing a number of color patches with known device control values, measuring the colors obtained-uniformity). Typically, the impact of these factors is minimized through careful design of the printing system. However
Vilkas, Marius J.; Lopez-Encarnacion, Juan M. [Department of Chemistry, University of Puerto Rico, P.O. Box 23346, San Juan, PR 00931-3346 (Puerto Rico); Ishikawa, Yasuyuki [Department of Chemistry, University of Puerto Rico, P.O. Box 23346, San Juan, PR 00931-3346 (Puerto Rico)], E-mail: yishikawa@uprrp.edu
2008-01-15T23:59:59.000Z
Relativistic multireference many-body Moller-Plesset perturbation theory (MR-MP) calculations have been performed on neonlike xenon, tungsten, and uranium ions. The 2s{sup -1}nl and 2p{sup -1}nl (n {<=} 5, l {<=} 4) energy levels, lifetimes and transition probabilities are reported. The second-order MR-MP calculation of energy levels included mass shifts, frequency-dependent first-order Breit correction and Lamb shifts. The calculated transition energies are compared with other theoretical and experimental data. The synthetic radiative spectra is presented for different wavelength regions.
Talbot, James P.
- sentatives from the public sector and NGOs. Business delegates are typically senior execu- tives and maintain a Pro- gramme which brings together business leaders and key public sector and civil society global trends and challenges: energy and natural resource security, cities, consumption, emerging
Standiford, Richard B.
exhibit typical foliar injury symptoms when exposed to ambient ozone, making them useful as bioindicators ozone monitors are not available. Bioindicators are often introduced plant species known as sentinels. They are known to be sensitive to ozone and will respond rapidly if they are given special care to ensure ozone
The calculated rovibronic spectrum of scandium hydride, ScH
Lodi, Lorenzo; Tennyson\\, Jonathan
2015-01-01T23:59:59.000Z
The electronic structure of six low-lying electronic states of scandium hydride, $X\\,{}^{1}\\Sigma^+$, $a\\,{}^{3}\\Delta$, $b\\,{}^{3}\\Pi$, $A\\,{}^{1}\\Delta$ $c\\,{}^{3}\\Sigma^+$, and $B\\,{}^{1}\\Pi$, is studied using multi-reference configuration interaction as a function of bond length. Diagonal and off-diagonal dipole moment, spin-orbit coupling and electronic angular momentum curves are also computed. The results are benchmarked against experimental measurements and calculations on atomic scandium. The resulting curves are used to compute a line list of molecular ro-vibronic transitions for $^{45}$ScH.
Proton induced activation in mercury: Comparison of measurements and calculations
Remec, Igor [ORNL; Glasgow, David C [ORNL; Haines, John R [ORNL; Johnson, Jeffrey O [ORNL
2008-01-01T23:59:59.000Z
Measurements and simulations of the proton beam interaction with the mercury target were performed to support Spallation Neutron Source design. Due to the abundance of isotopes produced in mercury, the long delay between the irradiation and the measurements, and the self-shielding of the mercury sample, the measurements were difficult to perform and the activities of several isotopes have large uncertainties. Calculations predicted the activities of the most reliably measured isotopes within 20%/40%; however, some large discrepancies were observed for some isotopes for which the measurements were considered less reliable. Predicted dose rates were in very good agreement with the measurements.
Accelerating Ab Initio Nuclear Physics Calculations with GPUs
Hugh Potter; Dossay Oryspayev; Pieter Maris; Masha Sosonkina; James Vary; Sven Binder; Angelo Calci; Joachim Langhammer; Robert Roth; Ümit Çatalyürek; Erik Saule
2014-12-18T23:59:59.000Z
This paper describes some applications of GPU acceleration in ab initio nuclear structure calculations. Specifically, we discuss GPU acceleration of the software package MFDn, a parallel nuclear structure eigensolver. We modify the matrix construction stage to run partly on the GPU. On the Titan supercomputer at the Oak Ridge Leadership Computing Facility, this produces a speedup of approximately 2.2x - 2.7x for the matrix construction stage and 1.2x - 1.4x for the entire run.