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Note: This page contains sample records for the topic "monochromator vls-pgm calculated" from the National Library of EnergyBeta (NLEBeta).
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We encourage you to perform a real-time search of NLEBeta
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1

Monochromator Crystal Glitch Library  

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

SSRL's Monochromator Crystal Glitch Library allows users to view glitch spectra online, list specific crystal orientations, and download PDF files of the glitch spectra. (Specialized Interface)

2

Pulsed-neutron monochromator  

DOE Patents [OSTI]

In one aspect, the invention is an improved pulsed-neutron monochromator of the vibrated-crystal type. The monochromator is designed to provide neutron pulses which are characterized both by short duration and high density. A row of neutron-reflecting crystals is disposed in a neutron beam to reflect neutrons onto a common target. The crystals in the row define progressively larger neutron-scattering angles and are vibrated sequentially in descending order with respect to the size of their scattering angles, thus generating neutron pulses which arrive simultaneously at the target. Transducers are coupled to one end of the crystals to vibrate them in an essentially non-resonant mode. The transducers propagate transverse waves in the crystal which progress longitudinally therein. The waves are absorbed at the undriven ends of the crystals by damping material mounted thereon. In another aspect, the invention is a method for generating neutron pulses characterized by high intensity and short duration.

Mook, H.A. Jr.

1984-01-01T23:59:59.000Z

3

Pulsed-neutron monochromator  

DOE Patents [OSTI]

In one aspect, the invention is an improved pulsed-neutron monochromator of the vibrated-crystal type. The monochromator is designed to provide neutron pulses which are characterized both by short duration and high density. A row of neutron-reflecting crystals is disposed in a neutron beam to reflect neutrons onto a common target. The crystals in the row define progressively larger neutron-scattering angles and are vibrated sequentially in descending order with respect to the size of their scattering angles, thus generating neutron pulses which arrive simultaneously at the target. Transducers are coupled to one end of the crystals to vibrate them in an essentially non-resonant mode. The transducers propagate transverse waves in the crystal which progress longitudinally therein. The wave are absorbed at the undriven ends of the crystals by damping material mounted thereon. In another aspect, the invention is a method for generating neutron pulses characterized by high intensity and short duration.

Mook, Jr., Herbert A. (Oak Ridge, TN)

1985-01-01T23:59:59.000Z

4

A dynamic focusing x-ray monochromator for a wiggler beam line at the SRS of the SERC Daresbury Laboratory  

SciTech Connect (OSTI)

A Si(220) double-crystal monochromator for the energy range 10--30 keV is presented. It will be used for EXAFS as well as powder diffraction measurements. To determine the requirements for this monochromator we looked, apart from mean considerations, at the requirements dictated by EXAFS in transmission mode. For good data analyses the proper shape, amplitude, and location at the energy axis of each wiggle is required. Moreover it is essential to separate the wiggles from background and noise. For the latter a high flux through the sample is desirable, which can be achieved by horizontal focusing of the beam. For that we have chosen to bend the second crystal sagitally. The sagittal bending radius is adjustable between 50 and 0.8 m, because for different energies different sagittal radii are necessary to focus the beam on the sample. The mean meridional radius of the second crystal is fixed at 130 m, which is an optimization for 20 keV. The meridional radius of the first crystal can be tuned between 100 and 500 m. When this radius is set to 130 m the energy resolution is calculated to be 6, 3, and 35 eV for 10, 20, and 30 keV (for perfectly bent crystals). By changing the meridional radius of the first crystal, future users of this monochromator can make the trade off between resolution and intensity. Movement of the monochromator exit beam, during a scan, will occur due to the monochromator geometry, but is reduced as much as possible by using an asymmetrically cut second crystal, with an asymmetry angle of 2.5{degree}. The average exit beam movement of the monochromator for a 1-keV scan is 20 {mu}m. For 40% of the energy range (10--30 keV) the exit beam position remains within 10 {mu}m. For the second crystal no translation stage is used.

De Bruijn, D.; Van Zuylen, P. (TNO Institute of Applied Physics, P.O. Box 155, 2600 AD Delft (Netherlands)); Kruizinga, G. (Netherlands Organization for Scientific Research (NWO), P.O. Box 93138, 2509 AC Den Haag (Netherlands) State University of Utrecht, Sorbonnelaan 16, 3508 TB Utrecht (Netherlands))

1992-01-01T23:59:59.000Z

5

High energy resolution, high angular acceptance crystal monochromator  

DOE Patents [OSTI]

A 4-bounce dispersive crystal monochromator reduces the bandpass of synchrotron radiation to a 10-50 meV range without sacrificing angular acceptance. The monochromator includes the combination of an asymmetrical channel-cut single crystal of lower order reflection and a symmetrical channel-cut single crystal of higher order reflection in a nested geometric configuration. In the disclosed embodiment, a highly asymmetrically cut (.alpha.=20) outer silicon crystal (4 2 2) with low order reflection is combined with a symmetrically cut inner silicon crystal (10 6 4) with high order reflection to condition a hard x-ray component (5-30 keV) of synchrotron radiation down to the .mu.eV-neV level. Each of the crystals is coupled to the combination of a positioning inchworm and angle encoder via a respective rotation stage for accurate relative positioning of the crystals and precise energy tuning of the monochromator.

Alp, Ercan E. (Bolingbrook, IL); Mooney, Timothy M. (Westmont, IL); Toellner, Thomas (Green Bay, WI)

1996-06-04T23:59:59.000Z

6

Optical system for high resolution spectrometer/monochromator  

DOE Patents [OSTI]

An optical system for use in a spectrometer or monochromator employing a mirror which reflects electromagnetic radiation from a source to converge with same in a plane is disclosed. A straight grooved, varied-spaced diffraction grating receives the converging electromagnetic radiation from the mirror and produces a spectral image for capture by a detector, target or like receiver. 11 figs.

Hettrick, M.C.; Underwood, J.H.

1988-10-11T23:59:59.000Z

7

Calculation  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation Proposed New Substation Sites Proposed Route BTRICGEGR-N GoodsMexico's EnergyCalculation of

8

Multilayers and Crystal for a Multi-bandpass Monochromator  

SciTech Connect (OSTI)

VESPERS beamline is a hard X-ray microprobe beamline dedicated to micro-diffraction and micro-fluorescence analysis at the Canadian Light Source; it requires multi-bandpass X-ray beams for different types of samples and experiments. A specially designed double crystal/multilayer monochromator was built for this purpose with three different bandpasses: 0.01%, 1.6% and 10%. The diffraction elements used for the monochromator have a triple-stripe design using Si(111) crystal as a single substrate with two differing stripes of Mo/B4C multilayers deposited thereon. The uncovered Si(111) section provides a 0.01% bandpass, while the periodic and depth-graded Mo/B4C multilayers provide 1.6% and 10% bandpasses, respectively. This paper outlines the requirements and specifications of the diffracting elements as well as the design, deposition and optimization of the multilayers. The performance of the deposited multilayer structures has been tested using Cu-Ka radiation line with a Huber diffractometer.

Feng, Renfei [Canadian Light Source, Saskatoon, Canada; Platonov, Yuriy [Rigaku Innovative Technologies, Inc., Auburn Hills, Michigan; Broadway, David [Rigaku Innovative Technologies, Inc., Auburn Hills, Michigan; Ice, Gene E [ORNL; Gerson, Andrea [University of South Australia; McIntyre, Stewart [University of Western Ontario, The

2008-01-01T23:59:59.000Z

9

Performance of a beam-multiplexing diamond crystal monochromator at the Linac Coherent Light Source  

SciTech Connect (OSTI)

A double-crystal diamond monochromator was recently implemented at the Linac Coherent Light Source. It enables splitting pulses generated by the free electron laser in the hard x-ray regime and thus allows the simultaneous operations of two instruments. Both monochromator crystals are High-Pressure High-Temperature grown type-IIa diamond crystal plates with the (111) orientation. The first crystal has a thickness of ?100 ?m to allow high reflectivity within the Bragg bandwidth and good transmission for the other wavelengths for downstream use. The second crystal is about 300 ?m thick and makes the exit beam of the monochromator parallel to the incoming beam with an offset of 600 mm. Here we present details on the monochromator design and its performance.

Zhu, Diling, E-mail: dlzhu@slac.stanford.edu; Feng, Yiping; Lemke, Henrik T.; Fritz, David M.; Chollet, Matthieu; Glownia, J. M.; Alonso-Mori, Roberto; Sikorski, Marcin; Song, Sanghoon; Williams, Garth J.; Messerschmidt, Marc; Boutet, Sébastien; Robert, Aymeric [Linac Coherent Light Source, SLAC National Accelerator Laboratory, Menlo Park, California 94025 (United States); Stoupin, Stanislav; Shvyd'ko, Yuri V. [Advanced Photon Source, Argonne National Laboratory, Lemont, Illinois 60439 (United States); Terentyev, Sergey A.; Blank, Vladimir D. [Technological Institute of Superhard and Novel Carbon Materials, Tsentralnaya str. 7a, Troitsk, Moscow 142190 (Russian Federation); Driel, Tim B. van [Linac Coherent Light Source, SLAC National Accelerator Laboratory, Menlo Park, California 94025 (United States); Center for Molecular Movies, Department of Physics, Technical University of Denmark, DK-2800 Lyngby (Denmark)

2014-06-15T23:59:59.000Z

10

Finite element analysis of the distortion of a crystal monochromator from synchrotron radiation thermal loading  

SciTech Connect (OSTI)

The first crystal of the Brown-Hower x-ray monochromator of the LBL-EXXON 54 pole wiggler beamline at Stanford Synchrotron Radiation Laboratory (SSRL) is subjected to intense synchrotron radiation. To provide an accurate thermal/structural analysis of the existing monochromator design, a finite element analysis (FEA) was performed. A very high and extremely localized heat flux is incident on the Si (220) crystal. The crystal, which possesses pronouncedly temperature-dependent orthotropic properties, in combination with the localized heat load, make the analysis ideally suited for finite element techniques. Characterization of the incident synchrotron radiation is discussed, followed by a review of the techniques employed in modeling the monochromator and its thermal/structural boundary conditions. The results of the finite element analysis, three-dimensional temperature distributions, surface displacements and slopes, and stresses, in the area of interest, are presented. Lastly, the effects these results have on monochromator output flux and resolution are examined.

Edwards, W.R.; Hoyer, E.H.; Thompson, A.C.

1985-10-01T23:59:59.000Z

11

Inclined monochromator for high heat-load synchrotron x-ray radiation  

DOE Patents [OSTI]

A double crystal monochromator is described including two identical, parallel crystals, each of which is cut such that the normal to the diffraction planes of interest makes an angle less than 90 degrees with the surface normal. Diffraction is symmetric, regardless of whether the crystals are symmetrically or asymmetrically cut, enabling operation of the monochromator with a fixed plane of diffraction. As a result of the inclination of the crystal surface, an incident beam has a footprint area which is elongated both vertically and horizontally when compared to that of the conventional monochromator, reducing the heat flux of the incident beam and enabling more efficient surface cooling. Because after inclination of the crystal only a fraction of thermal distortion lies in the diffraction plane, slope errors and the resultant misorientation of the diffracted beam are reduced. 11 figures.

Khounsary, A.M.

1994-02-15T23:59:59.000Z

12

Component/OEM XC-HR50 High Frame Rate Monochrome Camera  

E-Print Network [OSTI]

Monochrome Camera B/W Progressive Scan Cameras #12;These new cameras expand the range of products in Sony's progressive scan and high-frame rate, compact camera line up! Introducing the newest additions to Sony's B/sec. for compatibility with slower vision systems using Sony XC-55 cameras. The XC-HR50 and XC-HR70 cameras incorporate

Demoulin, Pascal

13

Subband coding of monochrome images over binary symmetric channels with error correction  

E-Print Network [OSTI]

for the degree of MASTER OF SCIENCE December 1992 Major Subject: Electrical Engineering SUBBAND CODING OF MONOCHROME IMAGES OVER BINARY SYMMETRIC CHANNELS WITH ERROR CORRECTION A Thesis by DENISE M. SHEPPARD Approved as to style and content by: V.... State diagram analysis of error recovery . B. Codebook design C. Performance results . 16 18 23 29 42 48 V VI ERROR CORRECTION A. Algorithm B. Performance Results CONCLUSION REFERENCES APPENDIX A . APPENDIX B . 52 54 61 67 70...

Sheppard, Denise M

2012-06-07T23:59:59.000Z

14

Current Status of the Synchrotron Radiation Center  

SciTech Connect (OSTI)

The Synchrotron Radiation Center (SRC) operates the Aladdin electron storage ring at energies of 800 MeV or 1 GeV in support of a broad range of national and international research programs. A low emittance configuration is in routine operation during 800-MeV shifts and offers improved photon flux density with about the same beam lifetime. An improved undulator compensation algorithm and new optical beam position monitors have been implemented improving beam stability and maintaining vertical beam size variations to < 2% peak-to-peak during undulator scanning. Instrumentation initiatives include construction of a modified Wadsworth beamline (7.8 - 50 eV) and a variable-line-spacing plane-grating monochromator (VLS-PGM, 75 - 2000 eV) to utilize radiation from a permanent magnet undulator. The Wadsworth beamline is being commissioned for photoelectron spectroscopy (PES) experiments using high-resolution Scienta analyzers. The VLS-PGM is being constructed for experiments that require higher photon energies and high flux density such as x-ray photoemission electron microscopy (X-PEEM) and x-ray absorption spectroscopy (XAS). It is scheduled to be available in early 2004. Recent research at the SRC has produced exciting results in a variety of fields, culminating in eight articles published in Physical Review Letters and three in Nature since October 2002, in addition to articles in many other publications. An outreach program offers research experiences for undergraduates and provides the general public with an awareness of synchrotron radiation. Hands-on workshops and activities on FTIR microscopy and X-PEEM are offered for graduate students and scientists. SRC sponsors a summer Research Experience for Undergraduates (REU) program and offers opportunities to non-research universities and high schools. Tours and educational events are coordinated with local civic groups and schools. Open houses are offered that include tours, demonstrations, and family activities.

Kinraide, R.; Moore, C.J.; Jacobs, K.D.; Severson, M.; Bissen, M.J.; Frazer, B.; Bisognano, J.J.; Bosch, R.A.; Eisert, D.; Fisher, M.; Green, M.A.; Gundelach, C.T.; Hansen, R.W.C.; Hochst, H.; Julian, R.L.; Keil, R.; Kleman, K.; Kubala, T.; Legg, R.A.; Pedley, B. [Synchrotron Radiation Center (United States)] [and others

2004-05-12T23:59:59.000Z

15

Calculator Policy  

E-Print Network [OSTI]

MA 16010 -- CALCULATOR POLICY. A ONE-LINE scientific calculator is REQUIRED. No other calculator is allowed. RECOMMENDED: TI-30Xa calculator

charlotb

2014-08-24T23:59:59.000Z

16

Calculator Policy  

E-Print Network [OSTI]

MA 15800 – Calculators – GOOD AND BAD. ONLY ONE-LINE scientific calculators are permitted. *RECOMMENDED CALCULATOR: TI-30XA(See Below).

charlotb

2014-06-10T23:59:59.000Z

17

Calculator Policy  

E-Print Network [OSTI]

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

2014-08-15T23:59:59.000Z

18

Calculator Policy  

E-Print Network [OSTI]

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 ...

charlotb

2014-12-17T23:59:59.000Z

19

Sagittal focusing Laue monochromator  

SciTech Connect (OSTI)

An x-ray focusing device generally includes a slide pivotable about a pivot point defined at a forward end thereof, a rail unit fixed with respect to the pivotable slide, a forward crystal for focusing x-rays disposed at the forward end of the pivotable slide and a rearward crystal for focusing x-rays movably coupled to the pivotable slide and the fixed rail unit at a distance rearward from the forward crystal. The forward and rearward crystals define reciprocal angles of incidence with respect to the pivot point, wherein pivoting of the slide about the pivot point changes the incidence angles of the forward and rearward crystals while simultaneously changing the distance between the forward and rearward crystals.

Zhong; Zhong (Stony Brook, NY), Hanson; Jonathan (Wading River, NY), Hastings; Jerome (Stanford, CA), Kao; Chi-Chang (Setauket, NY), Lenhard; Anthony (Medford, NY), Siddons; David Peter (Cutchogue, NY), Zhong; Hui (Coram, NY)

2009-03-24T23:59:59.000Z

20

Efficiency and stray light measurements and calculations of diffraction gratings for the Advanced Light Source  

SciTech Connect (OSTI)

Water-cooled gratings manufactured for spherical grating monochromators of the Advanced Light Source beamlines 7.0, 8.0, and 9.0 were measured with the laser plasma source and reflectometer in the Center for X-ray Optics at Lawrence Berkeley Laboratory. The square-wave gratings are ion milled into the polished electroless nickel surface after patterning by holographic photolithography. Absolute efficiency data are compared with exact electromagnetic theory calculation. Interorder stray light and groove depths can be estimated from the measurements.

McKinney, W.R.; Mossessian, D. (Accelerator and Fusion Research Division, Advanced Light Source, Lawrence Berkeley Laboratory, Berkeley, California 94720 (United States)); Gullikson, E. (Materials Sciences Division, Center for X-ray Optics, Lawrence Berkeley Laboratory, Berkeley, California 94720 (United States)); Heimann, P. (Accelerator and Fusion Research Division, Advanced Light Source, Lawrence Berkeley Laboratory, Berkeley, California 94720 (United States))

1995-02-01T23:59:59.000Z

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


21

Efficiency and stray light measurements and calculations of diffraction gratings for the ALS  

SciTech Connect (OSTI)

Water cooled gratings manufactured for spherical grating monochromators of the Advanced Light Source beamlines 7.0, 8.0 and 9.0 were measured with the laser plasma source and reflectometer in the Center for X-ray Optics at LBL. The square-wave gratings are ion-milled into the polished electroless nickel surface after patterning by holographic photolithography. Absolute efficiency data are compared with exact electromagnetic theory calculation. Inter-order stray light and groove depths can be estimated from the measurements.

McKinney, W.R.; Mossessian, D.; Gullikson, E.; Heimann, P.

1994-07-01T23:59:59.000Z

22

Performance and application of a double-crystal monochromator in the energy region 800 less than or equal to h. nu. less than or equal to 4500 eV  

SciTech Connect (OSTI)

The performance and application of an ultra-high-vacuum compatible constant-deviation double-crystal monochromator (JUMBO) in operation at SSRL is demonstrated. The monochromator can be operated with any of four pairs of crystals interchangeable in situ. An electronic-maximum-search feedback loop optimizes the intensity of the spatially fixed outgoing beam as the photon energy is scanned. The monochromatic beam is focussed (approx. 1.5 mm x 5 mm) onto the sample by a toroidal mirror. Monochromator crystals of beryl(10 anti 10), InSb(111) and Ge(111) have been tested in the energy regions 800 to 1540 eV, 1690 to 4000 eV and 1930 to 4500 eV, respectively. The performance of these crystals with regard to the resolution, the intensity, the level of scattered light, and the contribution of higher orders have been determined. Various effects arising from a radiation-induced temperature gradient in the monochromator crystals are discussed.

Hussain, Z.; Umbach, E.; Shirley, D.A.; Stoehr, V.; Feldhaus, J.

1981-07-01T23:59:59.000Z

23

MA 22400 -- CALCULATOR POLICY  

E-Print Network [OSTI]

MA 22400 -- CALCULATOR POLICY. A ONE-LINE scientific calculator is REQUIRED. No other calculator is allowed. RECOMMENDED: TI-30Xa calculator

OwenDavis

2014-08-22T23:59:59.000Z

24

Analysis of Nitro-Polycyclic Aromatic Hydrocarbons in Conventional Diesel and Fischer--Tropsch Diesel Fuel Emissions Using Electron Monochromator-Mass Spectrometry  

SciTech Connect (OSTI)

The presence of nitro-polycyclic aromatic hydrocarbons (NPAHs) in diesel fuel emissions has been studied for a number of years predominantly because of their contribution to the overall health and environmental risks associated with these emissions. Electron monochromator-mass spectrometry (EM-MS) is a highly selective and sensitive method for detection of NPAHs in complex matrixes, such as diesel emissions. Here, EM-MS was used to compare the levels of NPAHs in fuel emissions from conventional (petroleum) diesel, ultra-low sulfur/low-aromatic content diesel, Fischer-Tropsch synthetic diesel, and conventional diesel/synthetic diesel blend. The largest quantities of NPAHs were detected in the conventional diesel fuel emissions, while the ultra-low sulfur diesel and synthetic diesel fuel demonstrated a more than 50% reduction of NPAH quantities when compared to the conventional diesel fuel emissions. The emissions from the blend of conventional diesel with 30% synthetic diesel fuel also demonstrated a more than 30% reduction of the NPAH content when compared to the conventional diesel fuel emissions. In addition, a correlation was made between the aromatic content of the different fuel types and NPAH quantities and between the nitrogen oxides emissions from the different fuel types and NPAH quantities. The EM-MS system demonstrated high selectivity and sensitivity for detection of the NPAHs in the emissions with minimal sample cleanup required.

Havey, C. D.; McCormick, R. L.; Hayes, R. R.; Dane, A. J.; Voorhees, K. J.

2006-01-01T23:59:59.000Z

25

How Do Calculators Calculate? Helmut Knaust  

E-Print Network [OSTI]

not convert numbers to base 2. They use a binary-coded decimal (BCD) system instead. Calculators can only

Knaust, Helmut

26

Original Impact Calculations  

Broader source: Energy.gov [DOE]

Original Impact Calculations, from the Tool Kit Framework: Small Town University Energy Program (STEP).

27

Multiphase flow calculation software  

DOE Patents [OSTI]

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

Fincke, James R. (Idaho Falls, ID)

2003-04-15T23:59:59.000Z

28

Calculating Vessel Volumes  

E-Print Network [OSTI]

This summarizes a demonstration at the "Metron" conference (April 2002, Yale University), using a computer program to calculate the capacity of pots drawn on the computer screen and then given one dimension (e.g., its ...

Younger, John G.

2003-01-01T23:59:59.000Z

29

Solar radiation intensity calculations  

E-Print Network [OSTI]

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...

Levine, Randolph Steven

1978-01-01T23:59:59.000Z

30

Geothermal Life Cycle Calculator  

SciTech Connect (OSTI)

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.

Sullivan, John

2014-03-11T23:59:59.000Z

31

Geothermal Life Cycle Calculator  

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

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.

Sullivan, John

32

Carbon Footprint Calculator  

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.

33

PROPOSED RESIDENTIAL ALTERNATIVE CALCULATION  

E-Print Network [OSTI]

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

34

Plutonium 239 Equivalency Calculations  

SciTech Connect (OSTI)

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

Wen, J

2011-05-31T23:59:59.000Z

35

Horizontal well IPR calculations  

SciTech Connect (OSTI)

This paper presents the calculation of near-wellbore skin and non-Darcy flow coefficient for horizontal wells based on whether the well is drilled in an underbalanced or overbalanced condition, whether the well is completed openhole, with a slotted liner, or cased, and on the number of shots per foot and phasing for cased wells. The inclusion of mechanical skin and the non-Darcy flow coefficient in previously published horizontal well equations is presented and a comparison between these equations is given. In addition, both analytical and numerical solutions for horizontal wells with skin and non-Darcy flow are presented for comparison.

Thomas, L.K.; Todd, B.J.; Evans, C.E.; Pierson, R.G.

1996-12-31T23:59:59.000Z

36

ARM - Relative Humidity Calculations  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc Documentation RUC :ProductsSCM Forcing Data DerivedInstruments Related LinksCalculatorsRelative

37

ARM - Index of Calculators  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcal Documentation(AVIRIS) ProductsAirborneOctober 11, 2011 [FacilityIndiaGVAX NewsCalculators Outreach Home Room

38

ENRAF gauge reference level calculations  

SciTech Connect (OSTI)

This document describes the method for calculating reference levels for Enraf Series 854 Level Detectors as installed in the tank farms. The reference level calculation for each installed level gauge is contained herein.

Huber, J.H., Fluor Daniel Hanford

1997-02-06T23:59:59.000Z

39

CALCULATING INTERIOR DAYLIGHT ILLUMINATION WITH A PROGRAMMABLE HAND CALCULATOR  

E-Print Network [OSTI]

Committee E-3.2, "Daylight: International RecommendationsCalculation of Natural Daylight," CIE PUBLICATION No. 16,Committee E-3.2, "Natural Daylight: Official Recommenda-

Bryan, Harvey J.

2013-01-01T23:59:59.000Z

40

CALCULATING INTERIOR DAYLIGHT ILLUMINATION WITH A PROGRAMMABLE HAND CALCULATOR  

E-Print Network [OSTI]

Committee E-3.2, "Daylight: International Recommendationsthe Calculation of Natural Daylight, 11 CIE PUBLICATION No.Committee E-3.2 1 "Natural Daylight: Official Recommenda-

Bryan, Harvey J.

2013-01-01T23:59:59.000Z

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


41

Two-axis sagittal focusing monochromator  

DOE Patents [OSTI]

An x-ray focusing device and method for adjustably focusing x-rays in two orthogonal directions simultaneously. The device and method can be operated remotely using two pairs of orthogonal benders mounted on a rigid, open frame such that x-rays may pass through the opening in the frame. The added x-ray flux allows significantly higher brightness from the same x-ray source.

Haas, Edwin G; Stelmach, Christopher; Zhong, Zhong

2014-05-13T23:59:59.000Z

42

Multiple wavelength X-ray monochromators  

DOE Patents [OSTI]

An improved apparatus and method is provided for separating input x-ray radiation containing first and second x-ray wavelengths into spatially separate first and second output radiation which contain the first and second x-ray wavelengths, respectively. The apparatus includes a crystalline diffractor which includes a first set of parallel crystal planes, where each of the planes is spaced a predetermined first distance from one another. The crystalline diffractor also includes a second set of parallel crystal planes inclined at an angle with respect to the first set of crystal planes where each of the planes of the second set of parallel crystal planes is spaced a predetermined second distance from one another. In one embodiment, the crystalline diffractor is comprised of a single crystal. In a second embodiment, the crystalline diffractor is comprised of a stack of two crystals. In a third embodiment, the crystalline diffractor includes a single crystal that is bent for focusing the separate first and second output x-ray radiation wavelengths into separate focal points. 3 figs.

Steinmeyer, P.A.

1992-11-17T23:59:59.000Z

43

Microcomputer programs for particulate control: section failure; baghouse; plume opacity prediction; and in-stack opacity calculator. Software  

SciTech Connect (OSTI)

IBM-PC usable versions of several computer models useful in particulate control are provided. The models were originally written for the TRS-80 Model I-III series of microcomputers and have been translated to run on the IBM-PC. The documentation for the TRS-80 versions applies to the IBM-PC versions. The programs are written in FORTRAN and are provided in both source (FORTRAN) and executable form. Some small machine language routines are used to format the screen for data entry. These routines limit the programs to IBM-PC and close clones. The minimum hardware requirements are 256K IBM-PC or close clone, a monochrome monitor, and a disk drive. A printer is useful but not required. The following computer programs are provided in the four-disk package: (1) ESP section failure model, (2) GCA/EPA baghouse model, (3) Plume opacity prediction model, and (4) In-stack opacity calculator. All the models are documented in EPA report Microcomputer Programs for Particulate Control, EPA-600/8-85-025a (PB86-146529). The models provide useful tools for those involved in particulate control.

Sparks, L.E.

1985-09-01T23:59:59.000Z

44

Computational Tools for Supersymmetry Calculations  

E-Print Network [OSTI]

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.

Howard Baer

2009-12-16T23:59:59.000Z

45

Calculation of the parameters of the X-ray diffraction station with adaptive segmented optics on the side beam from the wiggler of the Sibir'-2 storage ring  

SciTech Connect (OSTI)

The mounting of an X-ray diffraction station on the side beam of a 19-pole superconducting wiggler makes it possible not only to use the central synchrotron radiation beam with a wavelength of 0.5 Angstrom-Sign , but also to solve problems requiring softer X rays at a synchrotron radiation (SR) intensity exceeding that for the beams from the bending magnet. A numerical simulation of the formation of photon beams from a source and their transmission through the elements of the station (and through the station as a whole) allows one to calculate the parameters of the station, compare it with the existing analogs, determine its potential and actual efficiency of its elements, and estimate the adjustment quality. A numerical simulation of the SR source on the side beam from the wiggler and the focusing channel (segmented condenser mirror, monochromator with sagittal focusing by the segmented second crystal, and segmented focusing mirror) has been performed. The sizes of the focus and the divergence of rays in it are determined with allowance for the finite sizes of segments. The intensity of radiation with a wavelength {lambda} = 1.0 Angstrom-Sign in the focus is determined taking into account the loss in the SR extraction channel and in the focusing channel. The values of the critical wavelength for the side beam from the wiggler and the wavelength resolution are calculated. The intensities in the X-ray diffraction pattern and its angular resolution are found.

Molodenskii, D. S.; Kheiker, D. M., E-mail: kheiker@ns.crys.ras.ru [Russian Academy of Sciences, Shubnikov Institute of Crystallography (Russian Federation); Korchuganov, V. N. [National Research Center Kurchatov Institute (Russian Federation); Konoplev, E. E. [NPO Luch (Russian Federation); Dorovatovskii, P. V. [National Research Center Kurchatov Institute (Russian Federation)

2012-05-15T23:59:59.000Z

46

Monte Carlo calculations of nuclei  

SciTech Connect (OSTI)

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.

Pieper, S.C. [Argonne National Lab., IL (United States). Physics Div.

1997-10-01T23:59:59.000Z

47

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,...

48

Calculate viscosities for 355 liquids  

SciTech Connect (OSTI)

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.

Yaws, C.L.; Lin, Xiaoyan; Li Bu (Lamar Univ., TX (United States))

1994-04-01T23:59:59.000Z

49

CALCULATING OPTICAL CONSTANTS OF GLAZING MATERIALS  

E-Print Network [OSTI]

Solar Energy CALCULATING OPTICAL CONSTANTS OF GLAZING MATERIALS Michael Rub August 1981 TWO-WEEK LOAN

Rubin, Michael

2013-01-01T23:59:59.000Z

50

FLAG-SGH Sedov calculations  

SciTech Connect (OSTI)

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

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

2012-06-25T23:59:59.000Z

51

RTU Comparison Calculator Enhancement Plan  

SciTech Connect (OSTI)

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.

Miller, James D.; Wang, Weimin; Katipamula, Srinivas

2014-03-31T23:59:59.000Z

52

Calculator Tips for TI-30XA  

E-Print Network [OSTI]

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 ...

Owen Davis

2013-01-04T23:59:59.000Z

53

Quantum transport calculations using periodic boundaryconditions  

SciTech Connect (OSTI)

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.

Wang, Lin-Wang

2004-06-15T23:59:59.000Z

54

Calculating Evolutionary Dynamics in Structured Populations  

E-Print Network [OSTI]

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

Nowak, Martin A.

55

Some Calculations for Cold Fusion Superheavy Elements  

E-Print Network [OSTI]

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

Zhong, X H; Ning, P Z

2004-01-01T23:59:59.000Z

56

Some Calculations for Cold Fusion Superheavy Elements  

E-Print Network [OSTI]

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

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

2004-10-18T23:59:59.000Z

57

Filter diagonalization of shell-model calculations  

SciTech Connect (OSTI)

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.

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

58

Calculators and Science and Engineering Calculus Occasionally ...  

E-Print Network [OSTI]

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 ...

1910-10-51T23:59:59.000Z

59

Evaluation Of Chemical Geothermometers For Calculating Reservoir...  

Open Energy Info (EERE)

Geothermometers For Calculating Reservoir Temperatures At Nevada Geothermal Power Plants Jump to: navigation, search OpenEI Reference LibraryAdd to library Conference Paper:...

60

PVWatts (R) Calculator India (Fact Sheet)  

SciTech Connect (OSTI)

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

Not Available

2014-01-01T23:59:59.000Z

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


61

Ris-M-2584 RELIABILITY CALCULATIONS  

E-Print Network [OSTI]

Risø-M-2584 RELIABILITY CALCULATIONS Improvements of methods intended for calculation of reliability of structures and systems Kurt E. Petersen Abstract. Risk and reliability analysis is increasingly being used in evaluations of plant safety and plant reliability. The analysis can be performed either

62

First principles calculations for analysis martensitic transformations  

SciTech Connect (OSTI)

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.

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

63

URANIUM MILL TAILINGS RADON FLUX CALCULATIONS  

E-Print Network [OSTI]

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

64

Quark model calculation of the EMC effect  

SciTech Connect (OSTI)

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.

Benesh, C.J.; Goldman, T.; Stephenson, G.J. Jr. [Los Alamos National Laboratory, NM (United States)

1993-10-01T23:59:59.000Z

65

AUXILIARY RATE CALCULATION The Budget Office  

E-Print Network [OSTI]

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

Weston, Ken

66

Unimolecular decomposition of methyltrichlorosilane: RRKM calculations  

SciTech Connect (OSTI)

Based on reaction thermochemistry and estimates of Arrhenius A-factors, it is expected that Si-C bond cleavage, C-H bond cleavage, and HCl elimination will be the primary channels for the unimolecular decomposition of methyltrichlorosilane. Using RRKM theory, we calculated rate constants for these three reactions. The calculations support the conclusion that these three reactions are the major decomposition pathways. Rate constants for each reaction were calculated in the high-pressure limit (800--1500 K) and in the falloff regime (1300--1500 K) for bath gases of both helium and hydrogen. These calculations thus provide branching fractions as well as decomposition rates. We also calculated bimolecular rate constants for the overall decomposition in the low-pressure limit. Interesting and surprising kinetic behavior of this system and the individual reactions is discussed. The reactivity of this chlorinated organosilane is compared to that of other organosilanes.

Osterheld, T.H.; Allendorf, M.D.; Melius, C.F.

1993-06-01T23:59:59.000Z

67

Relativistic QRPA calculation of muon capture rates  

E-Print Network [OSTI]

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.

T. Marketin; N. Paar; T. Niksic; D. Vretenar

2009-03-30T23:59:59.000Z

68

Calculated structures and fluoride affinities for fluorides  

SciTech Connect (OSTI)

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.

O'Keeffe, M.

1986-07-23T23:59:59.000Z

69

IAEA sodium void reactivity benchmark calculations  

SciTech Connect (OSTI)

In this paper, the IAEA-1 992 ``Benchmark Calculation of Sodium Void Reactivity Effect in Fast Reactor Core`` problem is evaluated. The proposed design is a large axially heterogeneous oxide-fueled fast reactor as described in Section 2; the core utilizes a sodium plenum above the core to enhance leakage effects. The calculation methods used in this benchmark evaluation are described in Section 3. In Section 4, the calculated core performance results for the benchmark reactor model are presented; and in Section 5, the influence of steel and interstitial sodium heterogeneity effects is estimated.

Hill, R.N.; Finck, P.J.

1992-12-01T23:59:59.000Z

70

IAEA sodium void reactivity benchmark calculations  

SciTech Connect (OSTI)

In this paper, the IAEA-1 992 Benchmark Calculation of Sodium Void Reactivity Effect in Fast Reactor Core'' problem is evaluated. The proposed design is a large axially heterogeneous oxide-fueled fast reactor as described in Section 2; the core utilizes a sodium plenum above the core to enhance leakage effects. The calculation methods used in this benchmark evaluation are described in Section 3. In Section 4, the calculated core performance results for the benchmark reactor model are presented; and in Section 5, the influence of steel and interstitial sodium heterogeneity effects is estimated.

Hill, R.N.; Finck, P.J.

1992-01-01T23:59:59.000Z

71

Assessment of seismic margin calculation methods  

SciTech Connect (OSTI)

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.

Kennedy, R.P.; Murray, R.C.; Ravindra, M.K.; Reed, J.W.; Stevenson, J.D.

1989-03-01T23:59:59.000Z

72

Use of computers for multicomponent distillation calculations  

E-Print Network [OSTI]

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...

Sullivan, Samuel Lane

1959-01-01T23:59:59.000Z

73

SIS Calculator User Guide 1 What's Inside  

E-Print Network [OSTI]

..................................................................................................................2 Measurement of Soil Moisture by Bonneville Power Administration (BPA) to provide general potential water and energy savings estimates, the calculator creates water and energy savings estimates associated with implementing SIS on a particular field

74

Historical river flow rates for dose calculations  

SciTech Connect (OSTI)

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

Carlton, W.H.

1991-06-10T23:59:59.000Z

75

Essential Value, Pmax, and Omax Automated Calculator  

E-Print Network [OSTI]

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 ...

Kaplan, Brent A.; Reed, Derek D.

2014-08-21T23:59:59.000Z

76

Medical physics calculations with MCNP: a primer  

E-Print Network [OSTI]

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...

Lazarine, Alexis D

2006-10-30T23:59:59.000Z

77

Hartree-Fock calculations of nuclear masses  

E-Print Network [OSTI]

Hartree-Fock calculations pertaining to the determination of nuclear binding energies throughout the whole chart of nuclides are reviewed. Such an approach is compared with other methods. Main techniques in use are shortly presented. Advantages and drawbacks of these calculations are also discussed with a special emphasis on the extrapolation towards nuclei far from the stability valley. Finally, a discussion of some selected results from light to superheavy nuclei, is given.

Quentin, P

1976-01-01T23:59:59.000Z

78

Signal probability calculations using partial functional manipulation  

E-Print Network [OSTI]

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...

Kodavarti, Ravishankar

1992-01-01T23:59:59.000Z

79

A demonstration of variance and covariance calculations using MAVARIC (Materials Accounting VARIance Calculator) and PROFF (PROcessing and Fuel Facilities calculator)  

SciTech Connect (OSTI)

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.

Barlich, G.L.; Nasseri, S.S.

1990-01-01T23:59:59.000Z

80

Improved Calculation of Thermal Fission Energy  

E-Print Network [OSTI]

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

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

2013-01-01T23:59:59.000Z

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


81

LCEs for Naval Reactor Benchmark Calculations  

SciTech Connect (OSTI)

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.

W.J. Anderson

1999-07-19T23:59:59.000Z

82

Sequential Covariance Calculation for Exoplanet Image Processing  

E-Print Network [OSTI]

Direct imaging of exoplanets involves the extraction of very faint signals from highly noisy data sets, with noise that often exhibits significant spatial, spectral and temporal correlations. As a results, a large number of post-processing algorithms have been developed in order to optimally decorrelate the signal from the noise. In this paper, we explore four such closely related algorithms, all of which depend heavily on the calculation of covariances between large data sets of imaging data. We discuss the similarities and differences between these methods, and demonstrate how the use sequential calculation techniques can significantly improve their computational efficiencies.

Savransky, Dmitry

2015-01-01T23:59:59.000Z

83

Nonperturbative calculations in light-front QED  

SciTech Connect (OSTI)

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.

Chabysheva, Sophia S. [Department of Physics, University of Minnesota-Duluth, Duluth, Minnesota 55812 (United States)

2010-12-22T23:59:59.000Z

84

Giant magnetoresistance calculated from first principles  

SciTech Connect (OSTI)

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.

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

85

Quantum Monte Carlo calculations for light nuclei  

SciTech Connect (OSTI)

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.

Wiringa, R.B.

1998-08-01T23:59:59.000Z

86

A PROCEDURE FOR CALCULATING INTERIOR DAYLIGHT ILLUMINATION WITH A PROGRAMMABLE HAND CALCULATOR  

E-Print Network [OSTI]

FOR CALCULATING INTERIOR DAYLIGHT ILLUMINATION WITH ACommittee E-3.2, "Daylight: International RecommendationsCalcula- tion of Natural Daylight," CIE PUBLICATION No. 16,

Bryan, H.J.

2010-01-01T23:59:59.000Z

87

Damien Allain Ingnieur recherche, dveloppement, calcul scientifique  

E-Print Network [OSTI]

, 5 articles publiés. · Administration du parc de machines de calculs Linux. 01/2003­03/2003 Ingénieur données, la réparation de code source en C/C++, de téléchargement de patch et de conversion d'image pour

88

2004 NET SYSTEM POWER CALCULATION COMMISSIONREPORT  

E-Print Network [OSTI]

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

89

FIRST PRINCIPLES CALCULATIONS OF TOKAMAK ENERGY TRANSPORT  

E-Print Network [OSTI]

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

Hammett, Greg

90

CALCULATING THE CARBON FOOTPRINT SUPPLY CHAIN FOR  

E-Print Network [OSTI]

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

Su, Xiao

91

New correlation calculates reliable paraffin solubilities  

SciTech Connect (OSTI)

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.

Yaws, C.L.; Pan, X. (Lamar Univ., Beaumont, TX (US))

1991-04-08T23:59:59.000Z

92

Oberseminar -ICP Temperature Calculation for Tribological  

E-Print Network [OSTI]

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

Harting, Jens

93

Calculation of Kinetics Parameters for the NBSR  

SciTech Connect (OSTI)

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

Hanson A. L.; Diamond D.

2012-03-06T23:59:59.000Z

94

CANISTER HANDLING FACILITY CRITICALITY SAFETY CALCULATIONS  

SciTech Connect (OSTI)

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].

C.E. Sanders

2005-04-07T23:59:59.000Z

95

CFD calculations of S809 aerodynamic characteristics  

SciTech Connect (OSTI)

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

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

1997-01-01T23:59:59.000Z

96

Improvements in EBR-2 core depletion calculations  

SciTech Connect (OSTI)

The need for accurate core depletion calculations in Experimental Breeder Reactor No. 2 (EBR-2) is discussed. Because of the unique physics characteristics of EBR-2, it is difficult to obtain accurate and computationally efficient multigroup flux predictions. This paper describes the effect of various conventional and higher order schemes for group constant generation and for flux computations; results indicate that higher-order methods are required, particularly in the outer regions (i.e. the radial blanket). A methodology based on Nodal Equivalence Theory (N.E.T.) is developed which allows retention of the accuracy of a higher order solution with the computational efficiency of a few group nodal diffusion solution. The application of this methodology to three-dimensional EBR-2 flux predictions is demonstrated; this improved methodology allows accurate core depletion calculations at reasonable cost. 13 refs., 4 figs., 3 tabs.

Finck, P.J.; Hill, R.N.; Sakamoto, S.

1991-01-01T23:59:59.000Z

97

Precipitation chemistry: its behavior and its calculation  

SciTech Connect (OSTI)

The purposes of this paper are twofold. The first of these is to present a rational basis for examining the aggregate set of scavenging-calculation techniques, and for guiding the reader in his course toward choosing the most appropriate technique for his particular application. The second purpose of this paper is to present a somewhat brief survey of our current understanding of scavenging and precipitation chemistry. Both objectives will be implemented by a flowchart approach, which attempts to draw the various facets of scavenging calculations together and present a generalized approach to the problem in total. The mathematical level of this paper is restricted to the presentation of the equations necessary to provide the reader with a basic appreciation of the fundamental concepts involved. References to more detailed mathematical treatments are cited at appropriate juncture points, for the reader interested in more detailed pursuit.

Hales, J.M.

1980-02-01T23:59:59.000Z

98

Calculation of source terms for NUREG-1150  

SciTech Connect (OSTI)

The source terms estimated for NUREG-1150 are generally based on the Source Term Code Package (STCP), but the actual source term calculations used in computing risk are performed by much smaller codes which are specific to each plant. This was done because the method of estimating the uncertainty in risk for NUREG-1150 requires hundreds of source term calculations for each accident sequence. This is clearly impossible with a large, detailed code like the STCP. The small plant-specific codes are based on simple algorithms and utilize adjustable parameters. The values of the parameters appearing in these codes are derived from the available STCP results. To determine the uncertainty in the estimation of the source terms, these parameters were varied as specified by an expert review group. This method was used to account for the uncertainties in the STCP results and the uncertainties in phenomena not considered by the STCP.

Breeding, R.J.; Williams, D.C.; Murfin, W.B.; Amos, C.N.; Helton, J.C.

1987-10-01T23:59:59.000Z

99

How to Calculate Molecular Column Density  

E-Print Network [OSTI]

The calculation of the molecular column density from molecular spectral (rotational or ro-vibrational) transition measurements is one of the most basic quantities derived from molecular spectroscopy. Starting from first principles where we describe the basic physics behind the radiative and collisional excitation of molecules and the radiative transfer of their emission, we derive a general expression for the molecular column density. As the calculation of the molecular column density involves a knowledge of the molecular energy level degeneracies, rotational partition functions, dipole moment matrix elements, and line strengths, we include generalized derivations of these molecule-specific quantities. Given that approximations to the column density equation are often useful, we explore the optically thin, optically thick, and low-frequency limits to our derived general molecular column density relation. We also evaluate the limitations of the common assumption that the molecular excitation temperature is con...

Mangum, Jeffrey G

2015-01-01T23:59:59.000Z

100

Analytic calculation of properties of holographic superconductors  

E-Print Network [OSTI]

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.

George Siopsis; Jason Therrien

2010-03-22T23:59:59.000Z

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


101

Diffusion Simulation and Lifetime Calculation at RHIC  

SciTech Connect (OSTI)

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.

Abreu,N.P.; Fischer, W.; Luo, Y.; Robert-Demolaize, G.

2009-01-02T23:59:59.000Z

102

Free Energy Calculation in MD Simulation  

E-Print Network [OSTI]

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

Nielsen, Steven O.

103

Calculations of Heat-Capacities of Adsorbates  

E-Print Network [OSTI]

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...

LAWRENCE, WR; Allen, Roland E.

1976-01-01T23:59:59.000Z

104

China 2050 Pathways Calculator | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of Inspector GeneralDepartmentAUDIT REPORTOpenWendeGuoCatalystPathways Calculator Jump to: navigation, search

105

Criticality Calculations for Step-2 GPHS Modules  

SciTech Connect (OSTI)

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.

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

106

Criticality calculations for Step-2 GPHS modules.  

SciTech Connect (OSTI)

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.

Hensen, Danielle Lynn; Lipinski, Ronald J.

2007-08-01T23:59:59.000Z

107

Agriculture-related radiation dose calculations  

SciTech Connect (OSTI)

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

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

1987-10-01T23:59:59.000Z

108

SEECAL: Program to calculate age-dependent  

SciTech Connect (OSTI)

This report describes the computer program SEECAL, which calculates specific effective energies (SEE) to specified target regions for ages newborn, 1 y, 5 y, 10 y, 15 y, a 70-kg adult male, and a 58-kg adult female. The dosimetric methodology is that of the International Commission on Radiological Protection (ICRP) and is generally consistent with the schema of the Medical Internal Radiation Dose committee of the US Society of Nuclear Medicine. Computation of SEEs is necessary in the computation of equivalent dose rate in a target region, for occupational or public exposure to radionuclides taken into the body. Program SEECAL replaces the program SEE that was previously used by the Dosimetry Research Group at Oak Ridge National Laboratory. The program SEE was used in the dosimetric calculations for occupational exposures for ICRP Publication 30 and is limited to adults. SEECAL was used to generate age-dependent SEEs for ICRP Publication 56, Part 1. SEECAL is also incorporated into DCAL, a radiation dose and risk calculational system being developed for the Environmental Protection Agency. Electronic copies of the program and data files and this report are available from the Radiation Shielding Information Center at Oak Ridge National Laboratory.

Cristy, M.; Eckerman, K.F.

1993-12-01T23:59:59.000Z

109

Cosmology calculations almost without general relativity  

E-Print Network [OSTI]

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.

Thomas F. Jordan

2004-12-08T23:59:59.000Z

110

Control Dewar Subcooler Heat Exchanger Calculations  

SciTech Connect (OSTI)

The calculations done to size the control dewar subcooler were done to obtain a sufficient subcooler size based on some conservative assumptions. The final subcooler design proposed in the design report will work even better because (1) It has more tubing length, and (2) will have already subcooled liquid at the inlet due to the transfer line design. The subcooler design described in the 'Design Report of the 2 Tesla Superconducting Solenoid for the Fermilab D0 Detector Upgrade' is the final design proposed. A short description of this design follows. The subcooler is constructed of 0.50-inch OD copper tubing with 1.0-inch diameter fins. It has ten and one half spirals at a 11.375-inch centerline diameter to provide 31 feet of tubing length. The liquid helium supply for the solenoid flows through the subcooler and then is expanded through a J-T valve. The subcooler spirals are immersed in the return two phase helium process stream. The return stream is directed over the finned tubing by an annulus created by a 10-inch pipe inside a 12-inch pipe. The transfer line from the refrigerator to the control dewar is constructed such that the liquid helium supply tube is in the refrigerator return stream, thereby subcooling the liquid up to the point where the u-tubes connect the transfer line to the control dewar. The subcooler within the control dewar will remove the heat picked up in the helium supply u-tube/bayonets. The attached subcooler/heat exchanger calculations were done neglecting any subcooling in the transfer line. All heat picked up in the transfer line from the refrigerator storage dewar to the control dewar is absorbed by the supply stream. The subcooler was sized such that the two phase supply fluid is subcooled at 1.7 atm pressure and when expanded through a JT valve to 1.45 atm pressure it is at a saturated liquid state. The calculations apply during steady state operation and at a flow rate of 16 g/s. The analysis of the heat exchanger was broken into two parts relating to the heat transfer mode taking place. The first part is considered the condensing part in which the helium supply stream is changed from two phase fluid to one phase liquid. The second part is the subcooling part where the liquid temperature is lowered, i.e.. subcooled. A summary of the calculations and results appears on the next page. The raw calculations follow the summary.

Rucinski, R.; /Fermilab

1993-10-04T23:59:59.000Z

111

Illustrative Calculation of Economics for Heat Pump and "Grid...  

Energy Savers [EERE]

Illustrative Calculation of Economics for Heat Pump and "Grid-Enabled" Water Heaters Illustrative Calculation of Economics for Heat Pump and "Grid-Enabled" Water Heaters Rate...

112

Building America Webinar: HVAC Right-Sizing Part 1-Calculating...  

Energy Savers [EERE]

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...

113

Multi-Fuel Boiler Efficiency Calculations  

E-Print Network [OSTI]

to calculate the heat losses, a complete stack analysis is required. In 1956 when Buna's paper was published, stack analysis was done by Orsat analysis which gave the composition of carbon dioxide, carbon monoxide and oxygen. Nitrogen was assumed to make... up the difference. It was known that sulfur dioxide (if present) would be absorbed with carbon dioxide. Table 2 shows the components in the stack gas and the analysis of the combustion air. The total analysis of the stack gas is estimated by a...

Likins, M. R., Jr.

1984-01-01T23:59:59.000Z

114

Nucleotide capacitance calculation for DNA sequencing  

SciTech Connect (OSTI)

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.

Lu, Jun-Qiang [ORNL; Zhang, Xiaoguang [ORNL

2008-01-01T23:59:59.000Z

115

SB EE Calculator | Argonne National Laboratory  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared0 ResourceAwards SAGE Awards A(SAPC) WorkingB.ProgramCalculator

116

USAID Carbon Calculator | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 No revisionEnvReviewNonInvasiveExplorationUT-gTagusparkCalculator Jump to: navigation, search Tool Summary LAUNCH

117

Sensitivity analysis of coupled criticality calculations  

SciTech Connect (OSTI)

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)

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

118

Electron mobility calculation for graphene on substrates  

SciTech Connect (OSTI)

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.

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

119

ANALYTICAL APPROACH TO TRANSIENT HEAT CONDUCTION IN COOLING LOAD CALCULATIONS  

E-Print Network [OSTI]

equation in cooling load calculations. The performance of nine different procedures (the four methods and

Michal Duška; Martin Barták; František Drkal; Jan Hensen

120

Benchmark On Sensitivity Calculation (Phase III)  

SciTech Connect (OSTI)

The sensitivities of the keff eigenvalue to neutron cross sections have become commonly used in similarity studies and as part of the validation algorithm for criticality safety assessments. To test calculations of the sensitivity coefficients, a benchmark study (Phase III) has been established by the OECD-NEA/WPNCS/EG UACSA (Expert Group on Uncertainty Analysis for Criticality Safety Assessment). This paper presents some sensitivity results generated by the benchmark participants using various computational tools based upon different computational methods: SCALE/TSUNAMI-3D and -1D, MONK, APOLLO2-MORET 5, DRAGON-SUSD3D and MMKKENO. The study demonstrates the performance of the tools. It also illustrates how model simplifications impact the sensitivity results and demonstrates the importance of 'implicit' (self-shielding) sensitivities. This work has been a useful step towards verification of the existing and developed sensitivity analysis methods.

Ivanova, Tatiana [IRSN; Laville, Cedric [IRSN; Dyrda, James [Atomic Weapons Establishment; Mennerdahl, Dennis [E. Mennerdahl Systems; Golovko, Yury [Institute of Physics and Power Engineering (IPPE), Obninsk, Russia; Raskach, Kirill [Institute of Physics and Power Engineering (IPPE), Obninsk, Russia; Tsiboulia, Anatoly [Institute of Physics and Power Engineering (IPPE), Obninsk, Russia; Lee, Gil Soo [Korea Institute of Nuclear Safety (KINS); Woo, Sweng-Woong [Korea Institute of Nuclear Safety (KINS); Bidaud, Adrien [Labratoire de Physique Subatomique et de Cosmolo-gie (LPSC); Patel, Amrit [NRC; Bledsoe, Keith C [ORNL; Rearden, Bradley T [ORNL; Gulliford, J. [OECD Nuclear Energy Agency

2012-01-01T23:59:59.000Z

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


121

Numerical calculations of ultrasonic fields. [STEALTH  

SciTech Connect (OSTI)

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.

Johnson, J.A.

1982-02-01T23:59:59.000Z

122

LMR thermal hydraulics calculations in the US  

SciTech Connect (OSTI)

A wide range of thermal hydraulics computer codes have been developed by various organizations in the US. These codes cover an extensive range of purposes from within-assembly-wise pin temperature calculations to plant wide transient analysis. The codes are used for static analysis, for analysis of protected anticipated transients, and for analysis of a wide range of unprotected transients for the more recent inherently safe LMR designs. Some of these codes are plant-specific codes with properties of a specific plant built into them. Other codes are more general and can be applied to a number of plants or designs. These codes, and the purposes for which they have been used, are described.

Dunn, F.E.; Malloy, D.J.; Mohr, D.

1987-04-27T23:59:59.000Z

123

Angular Size-Redshift: Experiment and Calculation  

E-Print Network [OSTI]

In this paper the next attempt is made to clarify the nature of the Euclidean behavior of the boundary in the angular size-redshift cosmological test. It is shown experimentally that this can be explained by the selection determined by anisotropic morphology and anisotropic radiation of extended radio sources. A catalogue of extended radio sources with minimal flux densities of about 0.01 Jy at 1.4 GHz was compiled for conducting the test. Without the assumption of their size evolution, the agreement between the experiment and calculation was obtained both in the Lambda CDM model (Omega_m=0.27 , Omega_v=0.73.) and the Friedman model (Omega = 0.1 ).

Amirkhanyan, V R

2015-01-01T23:59:59.000Z

124

A Calculable Toy Model of the Landscape  

E-Print Network [OSTI]

Motivated by recent discussions of the string-theory landscape, we propose field-theoretic realizations of models with large numbers of vacua. These models contain multiple U(1) gauge groups, and can be interpreted as deconstructed versions of higher-dimensional gauge theory models with fluxes in the compact space. We find that the vacuum structure of these models is very rich, defined by parameter-space regions with different classes of stable vacua separated by boundaries. This allows us to explicitly calculate physical quantities such as the supersymmetry-breaking scale, the presence or absence of R-symmetries, and probabilities of stable versus unstable vacua. Furthermore, we find that this landscape picture evolves with energy, allowing vacua to undergo phase transitions as they cross the boundaries between different regions in the landscape. We also demonstrate that supergravity effects are crucial in order to stabilize most of these vacua, and in order to allow the possibility of cancelling the cosmological constant.

Keith R. Dienes; Emilian Dudas; Tony Gherghetta

2005-04-22T23:59:59.000Z

125

Ab initio calculation of the Hoyle state  

E-Print Network [OSTI]

The Hoyle state plays a crucial role in the hydrogen burning of stars heavier than our sun and in the production of carbon and other elements necessary for life. This excited state of the carbon-12 nucleus was postulated by Hoyle [1] as a necessary ingredient for the fusion of three alpha particles to produce carbon at stellar temperatures. Although the Hoyle state was seen experimentally more than a half century ago [2,3], nuclear theorists have not yet uncovered the nature of this state from first principles. In this letter we report the first ab initio calculation of the low-lying states of carbon-12 using supercomputer lattice simulations and a theoretical framework known as effective field theory. In addition to the ground state and excited spin-2 state, we find a resonance at -85(3) MeV with all of the properties of the Hoyle state and in agreement with the experimentally observed energy. These lattice simulations provide insight into the structure of this unique state and new clues as to the amount of fine-tuning needed in nature for the production of carbon in stars.

Evgeny Epelbaum; Hermann Krebs; Dean Lee; Ulf-G. Meißner

2011-01-13T23:59:59.000Z

126

Supporting Calculations For Submerged Bed Scrubber Condensate Disposal Preconceptual Study  

SciTech Connect (OSTI)

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

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

2012-09-18T23:59:59.000Z

127

SUBJECT: CALCULATION OF JOB CREATION THROUGH RECOVERY ACT FUNDING...  

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

SUBJECT: CALCULATION OF JOB CREATION THROUGH RECOVERY ACT FUNDING SUBJECT: CALCULATION OF JOB CREATION THROUGH RECOVERY ACT FUNDING wpn10-14asep10-07aeecbg10-08a.pdf More...

128

TDHF fusion calculations for spherical+deformed systems  

E-Print Network [OSTI]

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.

A. S. Umar; V. E. Oberacker

2006-04-04T23:59:59.000Z

129

MATLAB Tutorial Getting Started with Calculations, Graphing and Programming  

E-Print Network [OSTI]

MATLAB Tutorial Getting Started with Calculations, Graphing and Programming Nicholas R. Kirchner UI 2 Calculations with MATLAB Standard Calculations and Variables Matrices and Vectors 3 Graphing NRK;Matrices and Vectors, Definitions MATLAB is short for MATrix LABoratory. It was built for high-speed matrix

Weinberger, Hans

130

Project W-320, 241-C-106 sluicing master calculation list  

SciTech Connect (OSTI)

This supporting document has been prepared to make the Master Calculation List readily retrievable. The list gives the status of the calculation (as-built, not used, applied, etc.), the calculation title, its originator, comments, and report number under which it was issued. Tank 241-C-106 has been included on the High Heat Load Watch List.

Bailey, J.W.

1998-08-07T23:59:59.000Z

131

STORM in Monte Carlo reactor physics calculations KAUR TUTTELBERG  

E-Print Network [OSTI]

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

Haviland, David

132

Entropy Calculations and the Third Law of Thermodynamics Chemistry 223  

E-Print Network [OSTI]

Entropy Calculations and the Third Law of Thermodynamics Chemistry 223 1. Entropy Calculations I We heat of fusion, sublimation, or vaporization) is added to the system, with no resulting change, 2014 #12;Entropy Calculations and the Third Law -2- Chemistry 223 STiT f = T0 Ti CP,i(T, P, N) T d

Ronis, David M.

133

Full Core, Heterogeneous, Time Dependent Neutron Transport Calculations with the 3D Code DeCART  

E-Print Network [OSTI]

for multi- dimensional reactor calculation." Atomkernenergiein Light Water Reactor calculations, which are processedlight water reactor diffusion calculations." Nuclear Science

Hursin, Mathieu

2010-01-01T23:59:59.000Z

134

Calculation of molecular free energies in classical potentials  

E-Print Network [OSTI]

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.

Farhi, Asaf

2015-01-01T23:59:59.000Z

135

CRC handbook of nuclear reactors calculations. Vol. III  

SciTech Connect (OSTI)

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.

Ronen, Y.

1986-01-01T23:59:59.000Z

136

A comparison of material balance calculations based on equilibrium ratios with Schilthuis balance calculations  

E-Print Network [OSTI]

and Liquid Phases for Assumed Initial Volume of 3, 900, 000, 000 Barrels. 31 ABSTRACT The theory of the material balance based on equihbrium ratios is described. The Kelley-Snyder field is described and a calculation of oil in place by the Schilthuis...& noglectbag the pres?ace of a water drive might ~ the high value of 4x 000, 000?000 barrels, and would if included, briag this value mox's into line with the others, Any water drive that would cause such effects would have to be from a limited aquifer...

Clanton, John L

2012-06-07T23:59:59.000Z

137

Transition-phase calculation of a large, heterogeneous-core LMFBR. [SIMMER-II calculations  

SciTech Connect (OSTI)

A mechanistic calculation of a complete transition-phase sequence for a large heterogeneous core LMFBR has been performed using SIMMER-II. Recriticalities occurred as the disruption progressed through a series of different subphases. The number and severity of recriticalities was directly related to the timing and scale of fuel removal and coherence of material motion. The energetics associated with transition-phase are not yet resolved but the understanding of the characteristics of disruption and the effects of uncertainties has been extended significantly.

Luck, L.B.; Bell, C.R.; Asprey, M.W.; DeVault, G.P.

1981-01-01T23:59:59.000Z

138

Comparing the accuracy of four-dimensional photon dose calculations with three-dimensional calculations using moving and deforming phantoms  

SciTech Connect (OSTI)

Purpose: Four-dimensional (4D) dose calculation algorithms, which explicitly incorporate respiratory motion in the calculation of doses, have the potential to improve the accuracy of dose calculations in thoracic treatment planning; however, they generally require greater computing power and resources than currently used for three-dimensional (3D) dose calculations. The purpose of this work was to quantify the increase in accuracy of 4D dose calculations versus 3D dose calculations. Methods: The accuracy of each dose calculation algorithm was assessed using measurements made with two phantoms. Specifically, the authors used a rigid moving anthropomorphic thoracic phantom and an anthropomorphic thoracic phantom with a deformable lung insert. To incorporate a clinically relevant range of scenarios, they programed the phantoms to move and deform with two motion patterns: A sinusoidal motion pattern and an irregular motion pattern that was extracted from an actual patient's breathing profile. For each combination of phantom and motion pattern, three plans were created: A single-beam plan, a multiple-beam plan, and an intensity-modulated radiation therapy plan. Doses were calculated using 4D dose calculation methods as well as conventional 3D dose calculation methods. The rigid moving and deforming phantoms were irradiated according to the three treatment plans and doses were measured using thermoluminescent dosimeters (TLDs) and radiochromic film. The accuracy of each dose calculation algorithm was assessed using measured-to-calculated TLD doses and a {gamma} analysis. Results: No significant differences were observed between the measured-to-calculated TLD ratios among 4D and 3D dose calculations. The {gamma} results revealed that 4D dose calculations had significantly greater percentage of pixels passing the 5%/3 mm criteria than 3D dose calculations. Conclusions: These results indicate no significant differences in the accuracy between the 4D and the 3D dose calculation methods inside the gross tumor volume. On the other hand, the film results demonstrated that the 4D dose calculations provided greater accuracy than 3D dose calculations in heterogeneous dose regions. The increase in accuracy of the 4D dose calculations was evident throughout the planning target volume.

Vinogradskiy, Yevgeniy Y.; Balter, Peter; Followill, David S.; Alvarez, Paola E.; White, R. Allen; Starkschall, George [Department of Radiation Physics, University of Texas M. D. Anderson Cancer Center, 1515 Holcombe Boulevard, Houston, Texas 77030 (United States); Department of Bioinformatics and Computational Biology, University of Texas M. D. Anderson Cancer Center, 1515 Holcombe Boulevard, Houston, Texas 77030 (United States); Department of Radiation Physics, University of Texas M. D. Anderson Cancer Center, 1515 Holcombe Boulevard, Houston, Texas 77030 (United States)

2009-11-15T23:59:59.000Z

139

Calculation of the compressibility factor and thermodynamic properties for methane  

E-Print Network [OSTI]

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...

Dowling, Dennis William

1966-01-01T23:59:59.000Z

140

Ghost Diffraction: Causal Explanation via Correlated Trajectory Calculations  

E-Print Network [OSTI]

We use trajectory calculations to successfully explain two-photon "ghost" diffraction, a phenomenon previously explained via quantum mechanical entanglement. The diffraction patterns are accumulated one photon pair at a time. The calculations are based on initial correlation of the trajectories in the crystal source and a trajectory-wave ordering interaction with a variant generator inherent in its structure. Details are presented in comparison with ordinary diffraction calculated with the same trajectory model.

Bill Dalton

2001-02-22T23:59:59.000Z

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


141

A Cosmology Calculator for the World Wide Web  

E-Print Network [OSTI]

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.

Edward L. Wright

2006-10-10T23:59:59.000Z

142

Microsoft Word - 911127_0 Parametric-Calculations_rel.doc  

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

7 Revision 0 Engineering Services for the Next Generation Nuclear Plant (NGNP) with Hydrogen Production NGNP Parametric Fuel and Reactor Pressure Vessel Temperature Calculations...

143

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...

144

Solid Waste Operations Complex (SWOC) Facilities Sprinkler System Hydraulic Calculations  

SciTech Connect (OSTI)

The attached calculations demonstrate sprinkler system operational water requirements as determined by hydraulic analysis. Hydraulic calculations for the waste storage buildings of the Central Waste Complex (CWC), T Plant, and Waste Receiving and Packaging (WRAP) facility are based upon flow testing performed by Fire Protection Engineers from the Hanford Fire Marshal's office. The calculations received peer review and approval prior to release. The hydraulic analysis program HASS Computer Program' (under license number 1609051210) is used to perform all analyses contained in this document. Hydraulic calculations demonstrate sprinkler system operability based upon each individual system design and available water supply under the most restrictive conditions.

KERSTEN, J.K.

2003-07-11T23:59:59.000Z

145

Examen de calcul matriciel Licence MASHS -MI -SPC, semestre 2  

E-Print Network [OSTI]

Examen de calcul matriciel Licence MASHS - MI - SPC, semestre 2 14 juin 2007 Durée de l'épreuve : 3

Lafont, Yves

146

Approach for calculating population doses using the CIDER computer code  

SciTech Connect (OSTI)

This report describes an approach for calculating radiation doses for the Hanford Environmental Dose Reconstruction Project. The approach utilizes the CIDER computer code.

Shipler, D.B.

1993-04-29T23:59:59.000Z

147

Formation enthalpies by mixing GGA and GGA + U calculations  

E-Print Network [OSTI]

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 ...

Jain, Anubhav

148

Calculation of tunneling rates across a barrier with continuous potential  

E-Print Network [OSTI]

Here, approximate, but accurate expressions for calculation of wavefunctions and tunneling rates are obtained using the method of uniform asymptotic expansion.

Sina Khorasani

2011-04-10T23:59:59.000Z

149

A Method for Calculating Reference Evapotranspiration on Daily Time Scales  

E-Print Network [OSTI]

Measures of reference evapotranspiration are essential for applications of agricultural management and water resources engineering. Using numerous esoteric variables, one can calculate daily reference evapotranspiration ...

Farmer, William

150

Burnup calculation methodology in the serpent 2 Monte Carlo code  

SciTech Connect (OSTI)

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)

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

151

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...

152

First-principles calculations of the electronic structure, phase...  

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

by combining the equation of states obtained from DFT calculations with the quasi-harmonic Debye model to take into account the entropy contribution to free energy. Local...

153

Model calculations of nuclear data for biologically-important elements  

SciTech Connect (OSTI)

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.

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

154

AHR 3/16/06 Equilibrium Flux Surface Calculations  

E-Print Network [OSTI]

preserved, with no flattening in edge stochastic region. · Assume zero net current (00 = 0). #12;#12;2 AHR 31 AHR 3/16/06 Equilibrium Flux Surface Calculations for W7AS and NCSX A. Reiman1, M. Zarnstorff1, D resonant magnetic field near plasma edge. Coil calculated to have little effect on rotational transform

Hudson, Stuart

155

Easier way to calculate E fields Equivalent to Coulomb's law  

E-Print Network [OSTI]

lines enter as leave closed surface the net is zero = ·= dAE AdE cos rr #12;Flux Calculate fluxGauss' Law Easier way to calculate E fields ­ Gauss' Law Equivalent to Coulomb's law Use ·= AE rr Let A become small so flux becomes integral over Gaussian surface Flux is proportional to net

Bertulani, Carlos A. - Department of Physics and Astronomy, Texas A&M University

156

IMPROVEMENTS TO THE RADIANT TIME SERIES METHOD COOLING LOAD CALCULATION  

E-Print Network [OSTI]

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

157

Integration of Ab Initio Nuclear Physics Calculations with Optimization Techniques  

E-Print Network [OSTI]

Integration of Ab Initio Nuclear Physics Calculations with Optimization Techniques Masha Sosonkina1 into the field of nuclear physics calculations where the objective functions are very complex and computationally the ab initio nuclear physics code MFDn and the VTDIRECT95 code for derivative-free op- timization. We

Sosonkina, Masha

158

RETI Resource Valuation Methodology Cost of Generation Calculator  

E-Print Network [OSTI]

) · Cost of equity investment in capital · Cost of financing capital · 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

159

Benchmark density functional theory calculations for nanoscale conductance  

E-Print Network [OSTI]

Benchmark density functional theory calculations for nanoscale conductance M. Strange,a I. S. The transmission functions are calculated using two different density functional theory methods, namely state density functional theory DFT . The resulting NEGF- DFT formalism provides a numerically efficient

Thygesen, Kristian

160

Appendix II. Calculation of Slope Factors for Naturally Occurring Radionuclides  

E-Print Network [OSTI]

Appendix II. Calculation of Slope Factors for Naturally Occurring Radionuclides In developing calculates the slope factors for the naturally occurring radionuclides under consideration. The Radionuclide products with half-lives of less than 6 months). As explained below, naturally occurring radionuclides

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


161

Optimization Online - Calculating optimal conditions for alloy and ...  

E-Print Network [OSTI]

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.

Aimen E. Gheribi

2010-12-21T23:59:59.000Z

162

CALCULATION OF THE NEUTRON NOISE INDUCED BY SHELL-MODE  

E-Print Network [OSTI]

CALCULATION OF THE NEUTRON NOISE INDUCED BY SHELL-MODE FISSION REACTORS CORE-BARREL VIBRATIONS-REGION SLAB REACTOR MODEL CARL SUNDE,* CHRISTOPHE DEMAZI�RE, and IMRE PÁZSIT Chalmers University of Technology for Publication October 12, 2005 The subject of this paper is the calculation of the in-core neutron noise induced

Demazière, Christophe

163

Overview of `classical' or `standardized' DPA calculation stemming from the  

E-Print Network [OSTI]

Overview of `classical' or `standardized' DPA calculation stemming from the reactor world. Colin English, NNL 7 April 2014 #12;2 Purpose · Overview of `classical' or `standardized' DPA calculation stemming from the reactor world. · Current Status · Details of accepted Methodology · Known Limitations

McDonald, Kirk

164

Calculating reactor transfer functions by Pade approximation via Lanczos algorithm  

E-Print Network [OSTI]

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

Pázsit, Imre

165

Texas LoanSTAR Program Savings Calculation Workbook  

E-Print Network [OSTI]

This is the report and manual for the Texas LoanSTAR Program Savings Calculation Workbook. The purpose of this report is to document the Texas LoanSTAR Program Savings Calculation Workbook to be used by the State Energy Conservation Office (SECO...

Liu, Z.; Baltazar-Cervantes, J. C.; Haberl, J. S.

2003-01-01T23:59:59.000Z

166

Processus communicants Communication synchrone CSP/CCS/-calcul  

E-Print Network [OSTI]

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

Grigoras, .Romulus

167

DATA FOR THE CALCULATION OF ALBEDOS FROM CONCRETE  

E-Print Network [OSTI]

DATA FOR THE CALCULATION OF ALBEDOS FROM CONCRETE IRON, LEAD, AND WATER FOR PHOTONS AND NEUTRONS for four materials: concrete, iron, lead, and water. Unlike previous compilations of albedo data, modern obtained by fits to results of Monte Carlo calculations for concrete,3 and later extended to water, iron

Shultis, J. Kenneth

168

General calculations using graphics hardware, with application to interactive caustics  

E-Print Network [OSTI]

General calculations using graphics hardware, with application to interactive caustics Chris Trendall and A. James Stewart iMAGIS­GRAVIR/IMAG and University of Toronto Abstract. Graphics hardware has general computation. This paper shows that graphics hardware can perform general calculations, which

Paris-Sud XI, Université de

169

STATE OF CALIFORNIA AREA WEIGHTED AVERAGE CALCULATION WORKSHEET: RESIDENTIAL  

E-Print Network [OSTI]

STATE OF CALIFORNIA AREA WEIGHTED AVERAGE CALCULATION WORKSHEET: RESIDENTIAL CEC-WS-2R (Revised 08/09) CALIFORNIA ENERGY COMMISSION Area Weighted Average Calculation Worksheet WS-2R Residential (Page 1 of 1) Site/Time: ____________________ HERS Provider: __________________ 2008 Residential Compliance Forms August 2009 This worksheet should

170

Benchmark problems and results for verifying resonance calculation methodologies  

SciTech Connect (OSTI)

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)

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

171

Calculation of Heating Values for the High Flux Isotope Reactor  

SciTech Connect (OSTI)

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.

Peterson, Joshua L [ORNL] [ORNL; Ilas, Germina [ORNL] [ORNL

2012-01-01T23:59:59.000Z

172

Practical calculation of amplitudes for electron-impact ionization  

SciTech Connect (OSTI)

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.

McCurdy, C. William; Horner, Daniel A.; Rescigno, Thomas N.

2001-02-01T23:59:59.000Z

173

CRC handbook of nuclear reactors calculations. Vol. II  

SciTech Connect (OSTI)

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.

Ronen, Y.

1986-01-01T23:59:59.000Z

174

Relativistic mean field calculations in neutron-rich nuclei  

SciTech Connect (OSTI)

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.

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

175

The Use of Graphics Calculator in a Matriculation Statistics Classroom: A Malaysian Perspective  

E-Print Network [OSTI]

mathematics: Why graphics calculator? Proceedings of the 2Learning statistics with graphics calculator: A case study.Learning statistics with graphics calculator: Students’

Krishnan, Saras; Idris, Noraini

2013-01-01T23:59:59.000Z

176

Calculation of Accurate Hexagonal Discontinuity Factors for PARCS  

SciTech Connect (OSTI)

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.

Pounders. J., Bandini, B. R. , Xu, Y, and Downar, T. J.

2007-11-01T23:59:59.000Z

177

Protein Thermostability Calculations Using Alchemical Free Energy Simulations  

E-Print Network [OSTI]

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

de Groot, Bert

178

Dose Rate Calculations for Rotary Mode Core Sampling Exhauster  

E-Print Network [OSTI]

This document provides the calculated estimated dose rates for three external locations on the Rotary Mode Core Sampling (RMCS) exhauster HEPA filter housing, per the request of Characterization Field Engineering.

Foust, D J

2000-01-01T23:59:59.000Z

179

Reactor physics calculation of BWR fuel bundles containing gadolinia  

E-Print Network [OSTI]

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 ...

Morales, Diego

1977-01-01T23:59:59.000Z

180

A computer program for HVDC converter station RF noise calculations  

SciTech Connect (OSTI)

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.

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

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


181

D0 Silicon Upgrade: Control Dewar Valve Calculations  

SciTech Connect (OSTI)

This engineering note documents the calculations that were done to support the valve size selection for the magnet flow control valve, EVMF in the solenoid control dewar. The size selected was a control valve with a Cv = 0.32.

Rucinski, Russ; /Fermilab

1995-10-20T23:59:59.000Z

182

AIM: Web-Based, Residential Energy Calculator for Homeowners  

E-Print Network [OSTI]

This paper discusses AIM, or Assess, Improve, Measure. AIM is an energy efficiency calculator for existing residences that has been developed to provide homeowners, realtors and builders with a method to rate the energy efficiency of an existing...

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

183

Statewide Air Emissions Calculations from Wind and Other Renewable  

E-Print Network [OSTI]

ESL-TR-13-07-01 STATEWIDE AIR EMISSIONS CALCULATIONS FROM WIND AND OTHER RENEWABLES SUMMARY REPORT A Report to the Texas Commission on Environmental Quality For the Period September 2012 – July 2013 Jeff Haberl... report, “Statewide Emissions Calculations From Wind and Other Renewables,” as required by the 79th Legislature. This work has been performed through a contract with the Texas Environmental Research Consortium (TERC). In this work the ESL is required...

Haberl, Jeff; Baltazar, Juan Carlos; Bahman, Yazdani; Claridge, David; Mao, Chunliu; Sandeep, Kota

184

Strategy Guideline: Accurate Heating and Cooling Load Calculations  

SciTech Connect (OSTI)

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

Burdick, A.

2011-06-01T23:59:59.000Z

185

Improved load models for multi-area reliability calculations  

E-Print Network [OSTI]

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...

Pathak, Sanjesh

1992-01-01T23:59:59.000Z

186

Reservoir rock-property calculations from thin section measurements  

E-Print Network [OSTI]

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...

Sneed, David Richard

1988-01-01T23:59:59.000Z

187

Scoping calculations of power sources for nuclear electric propulsion  

SciTech Connect (OSTI)

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.

Difilippo, F.C. [Oak Ridge National Lab., TN (United States)] [Oak Ridge National Lab., TN (United States)

1994-05-01T23:59:59.000Z

188

CRC handbook of nuclear reactors calculations. Vol. I  

SciTech Connect (OSTI)

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.

Ronen, Y.

1986-01-01T23:59:59.000Z

189

Water coning calculations for vertical and horizontal wells  

E-Print Network [OSTI]

Breakthrough Time WOR after Breakthrough RATE SENSITIVITY 8 12 13 16 WATER CONING CALCULATIONS FOR HIGH MOBILITY RATIOS . . 19 Method of Developing Correlations Correlations for a Vertical Well Correlations for a Horizontal Well Discussion 19 26... APPENDIX E: BASE CASE AND SIMULATION RUNS FOR HORIZONTAL WELLS 98 APPENDIX F: TEST CASES AND RESULTS FOR HORIZONTAL WELLS 100 APPENDIX G: ADDINGTON'S METHOD APPENDIX H: CALCULATION OF HEIGHT h~ APPENDIX I: BASE CASE AND SIMULATION RUN SUMMARY...

Yang, Weiping

1990-01-01T23:59:59.000Z

190

ESTIMATING THE UNCERTAINTY IN REACTIVITY ACCIDENT NEUTRONIC CALCULATIONS  

SciTech Connect (OSTI)

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.

DIAMOND,D.J.; YANG,C.Y.; ARONSON,A.L.

1998-10-26T23:59:59.000Z

191

Estimating the uncertainty in reactivity accident neutronic calculations  

SciTech Connect (OSTI)

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.

Diamond, D.J.; Yang, C.Y.; Aronson, A.L.

1998-12-31T23:59:59.000Z

192

Iterative acceleration methods for Monte Carlo and deterministic criticality calculations  

SciTech Connect (OSTI)

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

Urbatsch, T.J.

1995-11-01T23:59:59.000Z

193

Global variance reduction for Monte Carlo reactor physics calculations  

SciTech Connect (OSTI)

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)

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

194

Formal Management Review of the Safety Basis Calculations Noncompliance  

SciTech Connect (OSTI)

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.

Altenbach, T J

2008-06-24T23:59:59.000Z

195

514 ASHRAE Transactions: Symposia Design cooling load calculation methods are, by the  

E-Print Network [OSTI]

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

196

Solar Reflectance Index Calculation Worksheet Instructions The purpose of this calculator is to enable contractors and homeowners to quickly and accurately  

E-Print Network [OSTI]

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

197

Calculation of size for bound-state constituents  

E-Print Network [OSTI]

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.

Stanislaw D. Glazek

2014-06-01T23:59:59.000Z

198

Benchmark calculations for elastic fermion-dimer scattering  

E-Print Network [OSTI]

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.

Shahin Bour; H. -W. Hammer; Dean Lee; Ulf-G. Meißner

2012-06-08T23:59:59.000Z

199

Can fusion coefficients be calculated from the depth rule ?  

E-Print Network [OSTI]

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.

A. N. Kirillov; P. Mathieu; D. Senechal; M. Walton

1992-09-28T23:59:59.000Z

200

Review of Axial Burnup Distribution Considerations for Burnup Credit Calculations  

SciTech Connect (OSTI)

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

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

2000-03-01T23:59:59.000Z

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


201

Theory and calculations of synchrotron instabilities and feedback-mechanism  

SciTech Connect (OSTI)

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.

Meijssen, T.E.M.

1981-08-12T23:59:59.000Z

202

On calculation of microlensing light curve by gravitational lens caustic  

E-Print Network [OSTI]

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.

M. B. Bogdanov

2001-02-02T23:59:59.000Z

203

Monte Carlo reactor calculation with substantially reduced number of cycles  

SciTech Connect (OSTI)

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)

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

204

Evaluation and validation of criticality codes for fuel dissolver calculations  

SciTech Connect (OSTI)

During the past ten years an OECD/NEA Criticality Working Group has examined the validity of criticality safety computational methods. International calculation tools which were shown to be valid in systems for which experimental data existed were demonstrated to be inadequate when extrapolated to fuel dissolver media. The spread of the results in the international calculation amounted to {plus minus} 12,000 pcm in the realistic fuel dissolver exercise n{degrees} 19 proposed by BNFL, and to {plus minus} 25,000 pcm in the benchmark n{degrees} 20 in which fissile material in solid form is surrounded by fissile material in solution. A theoretical study of the main physical parameters involved in fuel dissolution calculations was performed, i.e. range of moderation, variation of pellet size and the fuel double heterogeneity effect. The APOLLO/P{sub IC} method developed to treat latter effect, permits us to supply the actual reactivity variation with pellet dissolution and to propose international reference values. The disagreement among contributors' calculations was analyzed through a neutron balance breakdown, based on three-group microscopic reaction rates solicited from the participants. The results pointed out that fast and resonance nuclear data in criticality codes are not sufficiently reliable. Moreover the neutron balance analysis emphasized the inadequacy of the standard self-shielding formalism (NITAWL in the international SCALE package) to account for {sup 238}U resonance mutual self-shielding in the pellet-fissile liquor interaction. Improvements in the up-dated 1990 contributions, as do recent complementary reference calculations (MCNP, VIM, ultrafine slowing-down CGM calculation), confirm the need to use rigorous self-shielding methods in criticality design-oriented codes. 6 refs., 11 figs., 3 tabs.

Santamarina, A.; Smith, H.J. (CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-lez-Durance (France)); Whitesides, G.E. (Oak Ridge National Lab., TN (United States))

1991-01-01T23:59:59.000Z

205

RADIATION DOSE CALCULATION FOR FUEL HANDLING FACILITY CLOSURE CELL EQUIPMENT  

SciTech Connect (OSTI)

This calculation evaluates the energy deposition rates in silicon, gamma and neutron flux spectra at various locations of interest throughout FHF closure cell. The physical configuration features a complex geometry, with particle flux attenuation of many orders of magnitude that cannot be modeled by computer codes that use deterministic methods. Therefore, in this calculation the Monte Carlo method was used to solve the photon and neutron transport. In contrast with the deterministic methods, Monte Carlo does not solve an explicit transport equation, but rather obtain answers by simulating individual particles, recording the aspects of interest of their average behavior, and estimates the statistical precision of the results.

D. Musat

2005-03-07T23:59:59.000Z

206

Calculation of TMD Evolution for Transverse Single Spin Asymmetry Measurements  

E-Print Network [OSTI]

The Sivers transverse single spin asymmetry (TSSA) is calculated and compared at different scales using the TMD evolution equations applied to previously existing extractions. We apply the Collins-Soper-Sterman (CSS) formalism, using the version recently developed by Collins. Our calculations rely on the universality properties of TMD-functions that follow from the TMD-factorization theorem. Accordingly, the non-perturbative input is fixed by earlier experimental measurements, including both polarized semi-inclusive deep inelastic scattering (SIDIS) and unpolarized Drell-Yan (DY) scattering. It is shown that recent COMPASS measurements are consistent with the suppression prescribed by TMD evolution.

S. Mert Aybat; Alexei Prokudin; Ted C. Rogers

2012-06-27T23:59:59.000Z

207

Phenomenological method of calculating microwave longitudinal coupling impedances  

SciTech Connect (OSTI)

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.

Giordano, S.; Votruba, J.

1980-05-01T23:59:59.000Z

208

Quantum statistical calculation of cluster abundances in hot dense matter  

E-Print Network [OSTI]

The cluster abundances are calculated from a quantum statistical approach taking into account in-medium corrections. For arbitrary cluster size the self-energy and Pauli blocking shifts are considered. Exploratory calculations are performed for symmetric matter at temperature $T=5$ MeV and baryon density $\\varrho=0.0156$ fm$^{-3}$ to be compared with the solar element distribution. It is shown that the abundances of weakly bound nuclei with mass number $4

Gerd Ropke

2014-07-01T23:59:59.000Z

209

Equation calculates activated carbon's capacity for adsorbing pollutants  

SciTech Connect (OSTI)

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.

Yaws, C.L.; Bu, L.; Nijhawan, S. (Lamar Univ., Beaumont, TX (United States))

1995-02-13T23:59:59.000Z

210

Recent Advances in Shell Evolution with Shell-Model Calculations  

E-Print Network [OSTI]

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.

Yutaka Utsuno; Takaharu Otsuka; Yusuke Tsunoda; Noritaka Shimizu; Michio Honma; Tomoaki Togashi; Takahiro Mizusaki

2014-09-16T23:59:59.000Z

211

Introduzione Matlab Carla Guerrini 1 IEEE-754 Calculators  

E-Print Network [OSTI]

1 Introduzione Matlab Carla Guerrini 1 IEEE-754 Calculators http://babbage.cs.qc.edu/IEEE-754 and Making an Impact http://www.ima.umn.edu/newsltrs/updates/summer03/ Introduzione Matlab Carla Guerrini 2 Introduzione all'ambiente Matlab #12;2 Introduzione Matlab Carla Guerrini 3 Riferimenti bibliografici · Guida

Guerrini, Carla

212

MATLAB Tutorial Getting Started with Calculations, Graphing and Programming  

E-Print Network [OSTI]

MATLAB Tutorial Getting Started with Calculations, Graphing and Programming Nicholas R. Kirchner University of Minnesota Thursday, August 30, 2012 #12;Outline 1 MATLAB installation NRK (University of Minnesota) MATLAB 2012.08.30 2 / 28 #12;Outline 1 MATLAB installation 2 The MATLAB UI NRK (University

Weinberger, Hans

213

Structural Analysis and Design Calculations for Hogan Project  

E-Print Network [OSTI]

Live Load Load Case 4: DL + WL With Cp = + 0.9 Load Case 5: DL + WL With Cp = - 0.3 The following. Introduction 2. Load calculations a. Dead Load b. Live Load c. Snow Load d. Wind Load e. Summary 3. Finite Element Model Analysis a. Element Description b. Loads c. Analysis i. Load Case 2 Truss Substructure ii

Mobasher, Barzin

214

MHD Stability Calculations of High-Quasi-Axisymmetric Stellarators  

E-Print Network [OSTI]

because the net toroidal current is zero or very small. However, in high-beta compact stellaratorsMHD Stability Calculations of High- Quasi-Axisymmetric Stellarators G. Y. Fu, L. P. Ku, N. Pomphrey the external kink modes. Most previous work has assumed cylindrical geometry and zero beta. In this work

215

MHD Stability Calculations of High-Quasi-Axisymmetric Stellarators  

E-Print Network [OSTI]

because the net toroidal current is zero or very small. However, in high-beta compact stellaratorsMHD Stability Calculations of High- Quasi-Axisymmetric Stellarators G. Y. Fu, L. P. Ku, N. Pomphrey kink modes. Most previous work has assumed cylindrical geometry and zero beta. In this work, extensive

216

Computationally Efficient Winding Loss Calculation with Multiple Windings, Arbitrary  

E-Print Network [OSTI]

windings occurs at the level of individual turns, the method could be applied, but its advantages are lessComputationally Efficient Winding Loss Calculation with Multiple Windings, Arbitrary Waveforms and Two- or Three-Dimensional Field Geometry C. R. Sullivan From IEEE Transactions on Power Electronics

217

Wind energy calculated from SAR and scatterometer satellite data  

E-Print Network [OSTI]

. · Offshore wind resources estimated from SAR · On WASP · Wind indexing based on scatterometer · Wake effects footprint 62 m footprint Wind field maps from SAR are valid for 10 m height #12;7 Slide no. 62 m 10 m Upwind1 Slide no. 4 Wind energy calculated from SAR and scatterometer satellite data Charlotte Bay

218

Adaptive Calculation of Variable Coefficients Elliptic Differential Equations via Wavelets  

E-Print Network [OSTI]

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

Averbuch, Amir

219

Gas-storage calculations yield accurate cavern, inventory data  

SciTech Connect (OSTI)

This paper discusses how determining gas-storage cavern size and inventory variance is now possible with calculations based on shut-in cavern surveys. The method is the least expensive of three major methods and is quite accurate when recorded over a period of time.

Mason, R.G. (Transcontinental Gas Pipeline Corp., Houston, TX (US))

1990-07-02T23:59:59.000Z

220

Calculation of dose to soft tisse from implanted beta sources  

E-Print Network [OSTI]

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...

Dauffy, Lucile

1998-01-01T23:59:59.000Z

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


221

Calculating Very Rough Market Share Using the Canadian Business Database  

E-Print Network [OSTI]

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

Thompson, Michael

222

Quantum Monte Carlo calculations of symmetric nuclear matter  

E-Print Network [OSTI]

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.

Stefano Gandolfi; Francesco Pederiva; Stefano Fantoni; Kevin E. Schmidt

2007-04-13T23:59:59.000Z

223

Improved Calculation of Core Loss With Nonsinusoidal Waveforms  

E-Print Network [OSTI]

. Comparison with experimental measure- ments in MnZn ferrite shows improved accuracy. The result may be op machines, transformers, inductors, and other static reactors, loss in the magnetic material is often pre of the flux density. It can be directly calculated from geometry and bulk resistivity in ferrites, and

224

Empirical Estimation of Biota Exposure Range for Calculation  

E-Print Network [OSTI]

for species lacking home range information Establish relationships between biota and sediment for BAF/BSAF calculation Identify potential applications for future sediment quality assessments #12;#12;#12;#12;BSAF = Ct.28 1 10 100 1000 10000 1 10 100 1000 10000 Sediment DDT (ug/kg dry) TissueDDT(ug/kgdry) BAF BSAF #12

225

On the ‘‘direct’’ calculation of thermal rate constants  

E-Print Network [OSTI]

required to obtain C f,s (t) is evaluated by a Lanczos iteration procedure which calculates only the nonzero eigenvalues. The propagation in complex time, t c =t?i??/2, is carried out using a Chebychev expansion. This method is seen to be both accurate...

Thompson, Ward H.; Miller, William H.

1995-03-01T23:59:59.000Z

226

Bohr Model Calculations for Atoms and Ions Frank Rioux  

E-Print Network [OSTI]

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

Rioux, Frank

227

A Lattice Energy Calculation for LiH Frank Rioux  

E-Print Network [OSTI]

energy operators for each of the electrons, and an electron-electron potential energy operator. HLi 1 2 r d d 2 1 r1 1 r2 1 r12 = When the trial wavefunction and the appropriate energy operator is usedA Lattice Energy Calculation for LiH Frank Rioux Lithium hydride is a white crystalline solid

Rioux, Frank

228

Alternative similarity renormalization group generators in nuclear structure calculations  

E-Print Network [OSTI]

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.

Nuiok M. Dicaire; Conor Omand; Petr Navratil

2014-08-22T23:59:59.000Z

229

GPA CALCULATION GPA = QUALITY POINTS DIVIDED BY QUALITY HOURS  

E-Print Network [OSTI]

. 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

Lawrence, Rick L.

230

Oxygen Toxicity Calculations by Erik C. Baker, P.E.  

E-Print Network [OSTI]

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

Read, Charles

231

Calculation of burnup of a black neutron absorber  

SciTech Connect (OSTI)

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.

Yudkevich, M. S., E-mail: umark@adis.vver.kiae.ru [Russian Research Centre Kurchatov Institute (Russian Federation)

2011-12-15T23:59:59.000Z

232

Atomic Structure Calculations from the Los Alamos Atomic Physics Codes  

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

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.

Cowan, R. D.

233

Using Graphical Representations to Support the Calculation of Infusion Parameters  

E-Print Network [OSTI]

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

Subramanian, Sriram

234

Fuzzy-probabilistic calculations of water-balance uncertainty  

SciTech Connect (OSTI)

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.

Faybishenko, B.

2009-10-01T23:59:59.000Z

235

Patent Citation Analysis: Calculating Science linkage based on Citing Motivation  

E-Print Network [OSTI]

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

Menczer, Filippo

236

RZ calculations for self shielded multigroup cross sections  

SciTech Connect (OSTI)

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)

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

237

Degree Day Calculations Dr. Nikki Rothwell, District Fruit IPM Educator  

E-Print Network [OSTI]

. For example, if the min/max thermometer indicates a low of 45 degrees F and a high of 75 degrees F F, then 10 degree days would have accumulated. Check your thermometer and make this calculation each toward your target number. Minimum and maximum temperatures should be recorded from a Min/Max thermometer

238

Dose calculation software for helical tomotherapy, utilizing patient CT data to calculate an independent three-dimensional dose cube  

SciTech Connect (OSTI)

Purpose: Treatment plans for the TomoTherapy unit are produced with a planning system that is integral to the unit. The authors have produced an independent dose calculation system, to enable plans to be recalculated in three dimensions, using the patient's CT data. Methods: Software has been written using MATLAB. The DICOM-RT plan object is used to determine the treatment parameters used, including the treatment sinogram. Each projection of the sinogram is segmented and used to calculate dose at multiple calculation points in a three-dimensional grid using tables of measured beam data. A fast ray-trace algorithm is used to determine effective depth for each projection angle at each calculation point. Calculations were performed on a standard desktop personal computer, with a 2.6 GHz Pentium, running Windows XP. Results: The time to perform a calculation, for 3375 points averaged 1 min 23 s for prostate plans and 3 min 40 s for head and neck plans. The mean dose within the 50% isodose was calculated and compared with the predictions of the TomoTherapy planning system. When the modified CT (which includes the TomoTherapy couch) was used, the mean difference for ten prostate patients, was -0.4% (range -0.9% to +0.3%). With the original CT (which included the CT couch), the mean difference was -1.0% (range -1.7% to 0.0%). The number of points agreeing with a gamma 3%/3 mm averaged 99.2% with the modified CT, 96.3% with the original CT. For ten head and neck patients, for the modified and original CT, respectively, the mean difference was +1.1% (range -0.4% to +3.1%) and 1.1% (range -0.4% to +3.0%) with 94.4% and 95.4% passing a gamma 4%/4 mm. The ability of the program to detect a variety of simulated errors has been tested. Conclusions: By using the patient's CT data, the independent dose calculation performs checks that are not performed by a measurement in a cylindrical phantom. This enables it to be used either as an additional check or to replace phantom measurements for some patients. The software has potential to be used in any application where one wishes to model changes to patient conditions.

Thomas, Simon J.; Eyre, Katie R.; Tudor, G. Samuel J.; Fairfoul, Jamie [Medical Physics Department, Addenbrooke's Hospital, Cambridge CB2 0QQ (United Kingdom)

2012-01-15T23:59:59.000Z

239

Benchmarking kinetic calculations of resistive wall mode stability  

SciTech Connect (OSTI)

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)].

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

240

Quantum Monte Carlo Calculations Applied to Magnetic Molecules  

SciTech Connect (OSTI)

We have calculated the equilibrium thermodynamic properties of Heisenberg spin systems using a quantum Monte Carlo (QMC) method. We have used some of these systems as models to describe recently synthesized magnetic molecules, and-upon comparing the results of these calculations with experimental data-have obtained accurate estimates for the basic parameters of these models. We have also performed calculations for other systems that are of more general interest, being relevant both for existing experimental data and for future experiments. Utilizing the concept of importance sampling, these calculations can be carried out in an arbitrarily large quantum Hilbert space, while still avoiding any approximations that would introduce systematic errors. The only errors are statistical in nature, and as such, their magnitudes are accurately estimated during the course of a simulation. Frustrated spin systems present a major challenge to the QMC method, nevertheless, in many instances progress can be made. In this chapter, the field of magnetic molecules is introduced, paying particular attention to the characteristics that distinguish magnetic molecules from other systems that are studied in condensed matter physics. We briefly outline the typical path by which we learn about magnetic molecules, which requires a close relationship between experiments and theoretical calculations. The typical experiments are introduced here, while the theoretical methods are discussed in the next chapter. Each of these theoretical methods has a considerable limitation, also described in Chapter 2, which together serve to motivate the present work. As is shown throughout the later chapters, the present QMC method is often able to provide useful information where other methods fail. In Chapter 3, the use of Monte Carlo methods in statistical physics is reviewed, building up the fundamental ideas that are necessary in order to understand the method that has been used in this work. With these ideas in hand, we then provide a detailed explanation of the current QMC method in Chapter 4. The remainder of the thesis is devoted to presenting specific results: Chapters 5 and 6 contain articles in which this method has been used to answer general questions that are relevant to broad classes of systems. Then, in Chapter 7, we provide an analysis of four different species of magnetic molecules that have recently been synthesized and studied. In all cases, comparisons between QMC calculations and experimental data allow us to distinguish a viable microscopic model and make predictions for future experiments. In Chapter 8, the infamous ''negative sign problem'' is described in detail, and we clearly indicate the limitations on QMC that are imposed by this obstacle. Finally, Chapter 9 contains a summary of the present work and the expected directions for future research.

Larry Engelhardt

2006-08-09T23:59:59.000Z

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


241

Identifying and bounding uncertainties in nuclear reactor thermal power calculations  

SciTech Connect (OSTI)

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)

Phillips, J.; Hauser, E.; Estrada, H. [Cameron, 1000 McClaren Woods Drive, Coraopolis, PA 15108 (United States)

2012-07-01T23:59:59.000Z

242

Uncertainties Associated with Theoretically Calculated N2-Broadened Half-Widths of H2O Lines  

E-Print Network [OSTI]

to be calculated theoretically. The accuracy of these calculated values depends on many factors such as the line-shape1 Uncertainties Associated with Theoretically Calculated N2- Broadened Half-Widths of H2O Lines Q-offs used in the theoretical calculations, we have carried out extensive numerical calculations of the N2

Gamache, Robert R.

243

Non-Born-Oppenheimer calculations of the BH molecule  

SciTech Connect (OSTI)

Variational calculations employing explicitly correlated Gaussian basis functions have been performed for the ground state of the boron monohydride molecule (BH) and for the boron atom (B). Up to 2000 Gaussians were used for each system. The calculations did not assume the Born-Oppenheimer (BO) approximation. In the optimization of the wave function, we employed the analytical energy gradient with respect to the Gaussian exponential parameters. In addition to the total nonrelativistic energies, we computed scalar relativistic corrections (mass-velocity and Darwin). With those added to the total energies, we estimated the dissociation energy of BH. The non-BO wave functions were also used to compute some expectation values involving operators dependent on the interparticle distances.

Bubin, Sergiy; Stanke, Monika; Adamowicz, Ludwik

2009-07-30T23:59:59.000Z

244

Ion beam energy spectrum calculation via dosimetry data deconvolution.  

SciTech Connect (OSTI)

The energy spectrum of a H{sup +} beam generated within the HERMES III accelerator is calculated from dosimetry data to refine future experiments. Multiple layers of radiochromic film are exposed to the beam. A graphic user interface was written in MATLAB to align the film images and calculate the beam's dose depth profile. Singular value regularization is used to stabilize the unfolding and provide the H{sup +} beam's energy spectrum. The beam was found to have major contributions from 1 MeV and 8.5 MeV protons. The HERMES III accelerator is typically used as a pulsed photon source to experimentally obtain photon impulse response of systems due to high energy photons. A series of experiments were performed to explore the use of Hermes III to generate an intense pulsed proton beam. Knowing the beam energy spectrum allows for greater precision in experiment predictions and beam model verification.

Harper-Slaboszewicz, Victor Jozef; Sharp, Andrew Clinton (A& M University, College Station, TX)

2010-10-01T23:59:59.000Z

245

Numerical calculations of ultrasonic fields I: transducer near fields  

SciTech Connect (OSTI)

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.

Johnson, J.A.

1982-03-01T23:59:59.000Z

246

Numerical calculations of ultrasonic fields I: transducer near fields  

SciTech Connect (OSTI)

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.

Johnson, J.A.

1982-04-01T23:59:59.000Z

247

Reactivity impact of delayed neutron spectra on MCNP calculations  

SciTech Connect (OSTI)

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.

Mosteller, R.D.; Werner, C.J.

2000-07-01T23:59:59.000Z

248

Variational calculations of the HT{sup +} rovibrational energies  

SciTech Connect (OSTI)

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.

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

249

Elastic properties of superconducting MAX phases from first principles calculations  

E-Print Network [OSTI]

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.

I. R. Shein; A. L. Ivanovskii

2010-06-03T23:59:59.000Z

250

Solid-State Calculation of Crystalline Color Superconductivity  

E-Print Network [OSTI]

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.

Cao, Gaoqing; Zhuang, Pengfei

2015-01-01T23:59:59.000Z

251

Solid-State Calculation of Crystalline Color Superconductivity  

E-Print Network [OSTI]

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.

Gaoqing Cao; Lianyi He; Pengfei Zhuang

2015-02-11T23:59:59.000Z

252

Calculation of the cross section for top quark production  

SciTech Connect (OSTI)

The authors summarize calculations of the cross section for top quark production at hadron colliders within the context of perturbative quantum chromodynamics, including resummation of the effects of initial-state soft gluon radiation to all orders in the strong coupling strength. In their approach they resume the universal leading-logarithm contributions, and they restrict the calculation to the region of phase space that is demonstrably perturbative. They compare the approach with other methods. They present predictions of the physical cross section as a function of the top quark mass in proton-antiproton reactions at center-of-mass energies of 1.8 and 2.0 TeV, and they discuss estimated uncertainties.

Berger, E.L.; Contopanagos, H. [Argonne National Lab., IL (United States). High Energy Physics Div.

1996-06-21T23:59:59.000Z

253

Quantum Monte Carlo Calculations of Light Nuclei Using Chiral Potentials  

E-Print Network [OSTI]

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.

J. E. Lynn; J. Carlson; E. Epelbaum; S. Gandolfi; A. Gezerlis; A. Schwenk

2014-11-09T23:59:59.000Z

254

Calculations of multiquark functions in effective models of strong interaction  

SciTech Connect (OSTI)

In this paper we present our results of the investigation of multiquark equations in the Nambu-Jona-Lasinio model with chiral symmetry of SU(2) group in the mean-field expansion. To formulate the mean-field expansion we have used an iteration scheme of solution of the Schwinger-Dyson equations with the fermion bilocal source. We have considered the equations for Green functions of the Nambu-Jona-Lasinio model up to third step for this iteration scheme. To calculate the high-order corrections to the mean-field approximation, we propose the method of the Legendre transformation with respect to the bilocal source, which allows effectively to take into account the symmetry constraints related with the chiral Ward identity. We discuss also the problem of calculating the multiquark functions in the mean-field expansion for Nambu-Jona-Lasinio-type models with other types of the multifermion sources.

Jafarov, R. G., E-mail: raufjafarov@bsu.az [Institute for Physical Problems of Baku State University (Azerbaijan); Rochev, V. E. [Institute of High Energy Physics, Theoretical Division (Russian Federation)] [Institute of High Energy Physics, Theoretical Division (Russian Federation)

2013-09-15T23:59:59.000Z

255

Effects of internal gain assumptions in building energy calculations  

SciTech Connect (OSTI)

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.

Christensen, C.; Perkins, R.

1981-01-01T23:59:59.000Z

256

Calculating the probability of detecting radio signals from alien civilizations  

E-Print Network [OSTI]

Although it might not be self-evident, it is in fact entirely possible to calculate the probability of detecting alien radio signals by understanding what types of extraterrestrial radio emissions can be expected and what properties these emissions can have. Using the Drake equation as the obvious starting point, and logically identifying and enumerating constraints of interstellar radio communications can yield the probability of detecting a genuine alien radio signal.

Marko Horvat

2007-07-14T23:59:59.000Z

257

Calculating the probability of detecting radio signals from alien civilizations  

E-Print Network [OSTI]

Although it might not be self-evident, it is in fact entirely possible to calculate the probability of detecting alien radio signals by understanding what types of extraterrestrial radio emissions can be expected and what properties these emissions can have. Using the Drake equation as the obvious starting point, and logically identifying and enumerating constraints of interstellar radio communications can yield the probability of detecting a genuine alien radio signal.

Horvat, Marko

2006-01-01T23:59:59.000Z

258

Validation of Criticality Safety Calculations with SCALE 6.2  

SciTech Connect (OSTI)

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.

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

259

Calculation of sensitivity coefficients for a neutron well logging tool  

E-Print Network [OSTI]

(Lsmsrsh, 1966; Bartine et al. , 1974; Duderstadt et al. , 1976). The straightforward (direct) calculation requires knowledge of the forward neutron flux, neutron cross section data, and detector responses (such as reaction rates) for each situation, i.... e. , the detector's responses are repeatedly com- puted for each change in the formation's composition. The perturbation (indirect) method requires knowledge of the forward neutron flux, detector response, and sd- joint neutron flux for a base...

Chen, Chien-Hsiang

2012-06-07T23:59:59.000Z

260

Numerical procedure for calculating temperature profiles in LMFBR coolant channels  

SciTech Connect (OSTI)

A new numerical procedure (which makes use of a weighted residuals procedure in space and a fully-implicit finite difference procedure in time), for calculating temperatures in an LMFBR coolant channel has been developed and incorporated into the Super System Code (SSC). This procedure is highly accurate on a nodal basis and has greatly increased computational efficiency as compared to the method formerly in SSC.

Horak, W.C.; Kennett, R.J.; Guppy, J.G.

1981-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "monochromator vls-pgm calculated" from the National Library of EnergyBeta (NLEBeta).
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261

Experiences with leak rate calculations methods for LBB application  

SciTech Connect (OSTI)

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.

Grebner, H.; Kastner, W.; Hoefler, A.; Maussner, G. [and others

1997-04-01T23:59:59.000Z

262

Quantum Monte Carlo Calculations of Symmetric Nuclear Matter  

SciTech Connect (OSTI)

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.

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

263

NAC-1 cask dose rate calculations for LWR spent fuel  

SciTech Connect (OSTI)

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.

CARLSON, A.B.

1999-02-24T23:59:59.000Z

264

New correlation accurately calculates water solubilities of aromatics  

SciTech Connect (OSTI)

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.

Yaws, C.L.; Bu, L.; Nijhawan, S. (Lamar Univ., Beaumont, TX (United States))

1994-08-29T23:59:59.000Z

265

Quantum Monte Carlo calculations of neutron-alpha scattering  

E-Print Network [OSTI]

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.

Kenneth M. Nollett; Steven C. Pieper; R. B. Wiringa; J. Carlson; G. M. Hale

2006-12-09T23:59:59.000Z

266

An alternative method for calculating the energy of gravitational waves  

E-Print Network [OSTI]

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.

Miroslav Sukenik; Jozef Sima

1999-09-21T23:59:59.000Z

267

Calculations in support of a potential definition of large release  

SciTech Connect (OSTI)

The Nuclear Regulatory Commission has stated a hierarchy of safety goals with the qualitative safety goals as Level I of the hierarchy, backed up by the quantitative health objectives as Level II and the large release guideline as Level III. The large release guideline has been stated in qualitative terms as a magnitude of release of the core inventory whose frequency should not exceed 10{sup -6} per reactor year. However, the Commission did not provide a quantitative specification of a large release. This report describes various specifications of a large release and focuses, in particular, on an examination of releases which have a potential to lead to one prompt fatality in the mean. The basic information required to set up the calculations was derived from the simplified source terms which were obtained from approximations of the NUREG-1150 source terms. Since the calculation of consequences is affected by a large number of assumptions, a generic site with a (conservatively determined) population density and meteorology was specified. At this site, various emergency responses (including no response) were assumed based on information derived from earlier studies. For each of the emergency response assumptions, a set of calculations were performed with the simplified source terms; these included adjustments to the source terms, such as the timing of the release, the core inventory, and the release fractions of different radionuclides, to arrive at a result of one mean prompt fatality in each case. Each of the source terms, so defined, has the potential to be a candidate for a large release. The calculations show that there are many possible candidate source terms for a large release depending on the characteristics which are felt to be important.

Hanson, A.L.; Davis, R.E.; Mubayi, V.

1994-05-01T23:59:59.000Z

268

NREL-Levelized Cost of Energy Calculator | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia: Energy Resources Jump to:46 -Energieprojekte3Informationof Energy Calculator Jump to: navigation, search

269

Community Wind Handbook/Calculate Simple Payback | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of Inspector GeneralDepartmentAUDITOhioOglesby,Sullivan,Information FeedColombia:|Calculate Simple Payback

270

Application of nuclear models to neutron nuclear cross section calculations  

SciTech Connect (OSTI)

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).

Young, P.G.

1982-01-01T23:59:59.000Z

271

WIPP Benchmark calculations with the large strain SPECTROM codes  

SciTech Connect (OSTI)

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.

Callahan, G.D.; DeVries, K.L. [RE/SPEC, Inc., Rapid City, SD (United States)

1995-08-01T23:59:59.000Z

272

Determination of hydrogen cluster velocities and comparison with numerical calculations  

SciTech Connect (OSTI)

The use of powerful hydrogen cluster jet targets in storage ring experiments led to the need of precise data on the mean cluster velocity as function of the stagnation temperature and pressure for the determination of the volume density of the target beams. For this purpose a large data set of hydrogen cluster velocity distributions and mean velocities was measured at a high density hydrogen cluster jet target using a trumpet shaped nozzle. The measurements have been performed at pressures above and below the critical pressure and for a broad range of temperatures relevant for target operation, e.g., at storage ring experiments. The used experimental method is described which allows for the velocity measurement of single clusters using a time-of-flight technique. Since this method is rather time-consuming and these measurements are typically interfering negatively with storage ring experiments, a method for a precise calculation of these mean velocities was needed. For this, the determined mean cluster velocities are compared with model calculations based on an isentropic one-dimensional van der Waals gas. Based on the obtained data and the presented numerical calculations, a new method has been developed which allows to predict the mean cluster velocities with an accuracy of about 5%. For this two cut-off parameters defining positions inside the nozzle are introduced, which can be determined for a given nozzle by only two velocity measurements.

Täschner, A.; Köhler, E.; Ortjohann, H.-W.; Khoukaz, A. [Institut für Kernphysik, Westfälische Wilhelms-Universität Münster, D-48149 Münster (Germany)] [Institut für Kernphysik, Westfälische Wilhelms-Universität Münster, D-48149 Münster (Germany)

2013-12-21T23:59:59.000Z

273

Multigroup calculations using VIM: A user's guide to ISOVIM  

SciTech Connect (OSTI)

Monte Carlo calculations have long been used to benchmark more a mate approximate solution methods for reactor physics problems. The power of VIM (ref 1) lies partly in the detailed geometrical representations incorporating the (generally) curved surfaces of combinatorial geometry, and partly in the fine energy detail of pointwise cross sections which are independent of the neutron spectrum. When differences arise between Monte Carlo and deterministic calculations, the question arises, is the error in the multigroup cross sections, in the treatment of transport effects, or in the mesh-based treatment of space in the deterministic calculation The answers may not be obvious, but may be identified by combining the exact geometry capability of VIM with the multigroup formalism. We can now run VIM in a multigroup mode by producing special VIM Material files which contain point-wise data describing multigroup data with histograms. This forces VIM to solve the multigroup problem with only three small code modifications. P[sub N] scattering is simulated with the usual tabulated angular distributions with 20 equally-sized scattering angle cosine meshes. This document describes the VIM multigroup capability, the procedures for generating multigroup cross sections for VIM, and their use. The multigroup cross section generating code, ISOVIM, is described, and benchmark testing is documented.

Blomquist, R.N.

1992-09-01T23:59:59.000Z

274

A general higher-order remap algorithm for ALE calculations  

SciTech Connect (OSTI)

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.

Chiravalle, Vincent P [Los Alamos National Laboratory

2011-01-05T23:59:59.000Z

275

WIPP shaft seal system parameters recommended to support compliance calculations  

SciTech Connect (OSTI)

The US Department of Energy plans to dispose of transuranic waste at the Waste Isolation Pilot Plant (WIPP), which is sited in southeastern New Mexico. The WIPP disposal facility is located approximately 2,150 feet (650 m) below surface in the bedded halite of the Salado Formation. Prior to initiation of disposal activities, the Department of Energy must demonstrate that the WIPP will comply with all regulatory requirements. Applicable regulations require that contaminant releases from the WIPP remain below specified levels for a period of 10,000 years. To demonstrate that the WIPP will comply with these regulations, the Department of Energy has requested that Sandia National Laboratories develop and implement a comprehensive performance assessment of the WIPP repository for the regulatory period. This document presents the conceptual model of the shaft sealing system to be implemented in performance assessment calculations conducted in support of the Compliance Certification Application for the WIPP. The model was developed for use in repository-scale calculations and includes the seal system geometry and materials to be used in grid development as well as all parameters needed to describe the seal materials. These calculations predict the hydrologic behavior of the system. Hence conceptual model development is limited to those processes that could impact the fluid flow through the seal system.

Hurtado, L.D.; Knowles, M.K. [Sandia National Labs., Albuquerque, NM (United States); Kelley, V.A.; Jones, T.L.; Ogintz, J.B. [INTERA Inc., Austin, TX (United States); Pfeifle, T.W. [RE/SPEC, Inc., Rapid City, SD (United States)

1997-12-01T23:59:59.000Z

276

Exact-to-precision generalized perturbation for neutron transport calculation  

SciTech Connect (OSTI)

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)

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

277

Calculation of nuclear masses using image reconstruction techniques  

SciTech Connect (OSTI)

Several methods have been developed to calculate and predict nuclear masses over the last 70 years. The accuracy of the present state-of-the-art nuclear mass models is impressive, because these quantities can be calculated with an average 0.05 % precision. However this precision level is still insufficient to deal with nuclear reactions of astrophysical interest, especially r-process ones. Different approaches exist to calculate nuclear masses, ranging from the simple Bethe-Weizsaecker Liquid Drop Formula (LDM) to the sophisticated Finite Range Droplet Model calculations or the microscopic Hartree-Fock-Bogoliuvob techniques from first principles, using Skyrme or Gogny parametrizations of the nucleon-nucleon interaction. Here we suggest a new method to calculate this fundamental property of the atomic nucleus, using a completely phenomenological point of view. Our method is based in the analysis of the differences between measured masses and LDM predictions, which contains information related to those ingredients not taken into account in the LDM formula, such as shell closures, nuclear deformations and residual nuclear interactions. The differences are arranged in a two dimensional plot which can be viewed as an incomplete image of the full chart of nuclides, equivalent to a product of the full image and a binary mask. In order to remove the distortions produced by this mask we employ an algorithm, well known in astronomy, used to remove artificial effects present in the astrophysical images collected through telescopes. This algorithm is called the CLEAN method. It is one of a number of methods which exists to deconvolve undesirable effects in images and to extrapolate or reconstruct missing parts in them. By using the CLEAN method we can fit measured masses with an r.m.s error of less than 100 keV. We have performed several checks and concluded that its utilization must be carried out carefully in order to obtain reliable results in the zone of unknown masses between the driplines. We also outline potential applications of the present approach.

Barea, J.; Frank, A.; Hirsch, J. G.; Lopez, J. C.; Morales, I.; Mendoza, J. [Instituto de Ciencias Nucleares, Universidad Nacional Autonoma de Mexico, Apartado Postal 70-543, 04510 Mexico, D.F. (Mexico); Velazquez, V. [Facultad de Ciencias, Universidad Nacional Autonoma de Mexico, 04510 Mexico, D.F. (Mexico)

2007-10-26T23:59:59.000Z

278

Investigation of the Accuracy of Calculation Methods for Conduction Transfer Functions of Building Construction  

E-Print Network [OSTI]

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...

Chen, Y.; Li, X.; Zhang, Q.; Spitler, J.; Fisher, D.

2006-01-01T23:59:59.000Z

279

Electric Field Calculations on Dry-Type Medium Voltage Current Transformers.  

E-Print Network [OSTI]

??This research presents potential and electric field calculations on medium voltage (MV) epoxy insulated outdoor current transformers (CTs) using a numeri-cal calculation approach. Two designs… (more)

Lakshmichand Jain, Sandeep Kumar

2012-01-01T23:59:59.000Z

280

Consistent neutron kinetics data generation for nodal transient calculations  

SciTech Connect (OSTI)

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)

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

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


281

Calculation of material properties and ray tracing in transformation media  

E-Print Network [OSTI]

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.

Schurig, D; Smith, D R

2006-01-01T23:59:59.000Z

282

Statewide Air Emissions Calculations from Energy Efficiency, Wind and Renewables  

E-Print Network [OSTI]

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... Speed (MPH) T u rb in e P o w er (k W h /h ) Hourly electricity produced vs on- site wind data acceptable for hourly modeling. Issue: hourly on-site data not always available. Calculating NOx Reductions from Wind Farms Energy...

Haberl, J.; Yazdani, B.; Culp, C.

283

Calculational comparison of DT, neon, and argon implosions  

SciTech Connect (OSTI)

A number of laboratories have been doing laser driven implosions of pure neon and argon gas as a diagnostic of the peak imploded conditions. The relationship of these implosions to DT implosions has been unclear. This paper will explore the physics of these higher Z gases and show that they are fundamentally easier to compress than DT gas. Specifically, this paper will show that, for the same initial mass density, and the same capsule design and drive conditions, the calculated peak compressed density is dependent on the type of fill gas, being substantially higher for Ne and Ar implosions than for DT implosions.

Stevens, J.C.

1980-10-28T23:59:59.000Z

284

Accelerating Ab Initio Nuclear Physics Calculations with GPUs  

E-Print Network [OSTI]

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.

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

285

L2-Logique, TD5 Calcul des propositions  

E-Print Network [OSTI]

L2-Logique, TD5 2007/08 Calcul des propositions 1 D´emonstrations Dans cette partie, utilisez le m´eta-th´eor standard. On interpr`ete ce syst`eme par l'alg`ebre de Boole standard. 2 - Est-ce que tout th´eor`eme de CP) (A B) | A, B FCP0 } 4 - Est-ce que toute tautologie est un th´eor`eme de CP0' ? 5 - Le m´eta-th´eor

Narboux, Julien

286

Proton induced activation in mercury: Comparison of measurements and calculations  

SciTech Connect (OSTI)

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.

Remec, Igor [ORNL; Glasgow, David C [ORNL; Haines, John R [ORNL; Johnson, Jeffrey O [ORNL

2008-01-01T23:59:59.000Z

287

Semiclassical framework for the calculation of transport anisotropies  

E-Print Network [OSTI]

and well-known phenomenon1?3 with applications in spintronics.4,5 Although the experimental observation of this anisotropic magnetoresistance #1;AMR#2; is rather direct?first accomplished as early as 1857?its theo- retical understanding is far from...; relies on calculating the transport relaxation time #2; from the scattering amplitudes w#1;k#1; ,k#1;#1;#2; between two states on the Fermi surface using 1 #2; =#3; d2k#1;#1;2#3;#2;2w#1;k#1;,k#1;#1;#2;#4;1 ? cos #4;k#1;k#1;#1;#5; . #1;1...

Vyborny, Karel; Kovalev, Alexey A.; Sinova, Jairo; Jungwirth, T.

2009-01-01T23:59:59.000Z

288

Calculation of nuclear matrix elements in neutrinoless double electron capture  

E-Print Network [OSTI]

We compute nuclear matrix elements for neutrinoless double electron capture on $^{152}$Gd, $^{164}$Er and $^{180}$W nuclei. Recent precise mass measurements for these nuclei have shown a large resonance enhancement factor that makes them the most promising candidates for observing this decay mode. We use an advanced energy density functional method which includes beyond mean-field effects such as symmetry restoration and shape mixing. Our calculations reproduce experimental charge radii and $B(E2)$ values predicting a large deformation for all these nuclei. This fact reduces significantly the values of the NMEs leading to half-lives larger than $10^{29}$ years for the three candidates.

Tomas R. Rodriguez; Gabriel Martinez-Pinedo

2012-03-05T23:59:59.000Z

289

Atomic data for astrophysics. Calculations, benchmarking and distribution  

SciTech Connect (OSTI)

Some recent R-matrix and distorted-wave calculations, done as part of the UK APAPNetwork, are presented. They are focused on some ions important for the EUV and the X-rays, in particular for the solar corona. A long-term and novel project to benchmark atomic data against laboratory and astrophysical data is summarised, highlighting new plasma diagnostics. The various ways in which the atomic data are made available to the various communities through e.g. the CHIANTI and the VAMDC EU framework are also presented.

Del Zanna, G. [Department of Applied Mathematics and Theoretical Physics University of Cambridge Wilberforce Road, Cambridge, CB3 0WA (United Kingdom)

2012-05-25T23:59:59.000Z

290

Envelope calculations for a low temperature neutron star  

E-Print Network [OSTI]

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...

McCoy, Robert Paul

1976-01-01T23:59:59.000Z

291

Proliferation Potential of Accelerator-Drive Systems: Feasibility Calculations  

SciTech Connect (OSTI)

Accelerator-driven systems for fissile materials production have been proposed and studied since the early 1950s. Recent advances in beam power levels for small accelerators have raised the possibility that such use could be feasible for a potential proliferator. The objective of this study is to review the state of technology development for accelerator-driven spallation neutron sources and subcritical reactors. Energy and power requirements were calculated for a proton accelerator-driven neutron spallation source and subcritical reactors to produce a significant amount of fissile material--plutonium.

Riendeau, C.D.; Moses, D.L.; Olson, A.P.

1998-11-01T23:59:59.000Z

292

Calculating and Communicating Program Results | Department of Energy  

Energy Savers [EERE]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustion |Energyon ArmedWaste andAccessCO2 Injection Begins in Illinois CO2SoftwareCalculating and

293

CALCULATION OF PULSED KICKER MAGNETIC FIELD ATTENUATION INSIDE BEAM CHAMBERS  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation Proposed New Substation Sites Proposed Route Segments (not drawn30:133PortableCALCULATION OF

294

Physics methods for calculating light water reactor increased performances  

SciTech Connect (OSTI)

The intensive use of light water reactors (LWRs) has induced modification of their characteristics and performances in order to improve fissile material utilization and to increase their availability and flexibility under operation. From the conceptual point of view, adequate methods must be used to calculate core characteristics, taking into account present design requirements, e.g., use of burnable poison, plutonium recycling, etc. From the operational point of view, nuclear plants that have been producing a large percentage of electricity in some countries must adapt their planning to the need of the electrical network and operate on a load-follow basis. Consequently, plant behavior must be predicted and accurately followed in order to improve the plant's capability within safety limits. The Belgonucleaire code system has been developed and extensively validated. It is an accurate, flexible, easily usable, fast-running tool for solving the problems related to LWR technology development. The methods and validation of the two computer codes LWR-WIMS and MICROLUX, which are the main components of the physics calculation system, are explained.

Vandenberg, C.; Charlier, A.

1988-11-01T23:59:59.000Z

295

Tissue Heterogeneity in IMRT Dose Calculation for Lung Cancer  

SciTech Connect (OSTI)

The aim of this study was to evaluate the differences in accuracy of dose calculation between 3 commonly used algorithms, the Pencil Beam algorithm (PB), the Anisotropic Analytical Algorithm (AAA), and the Collapsed Cone Convolution Superposition (CCCS) for intensity-modulated radiation therapy (IMRT). The 2D dose distributions obtained with the 3 algorithms were compared on each CT slice pixel by pixel, using the MATLAB code (The MathWorks, Natick, MA) and the agreement was assessed with the {gamma} function. The effect of the differences on dose-volume histograms (DVHs), tumor control, and normal tissue complication probability (TCP and NTCP) were also evaluated, and its significance was quantified by using a nonparametric test. In general PB generates regions of over-dosage both in the lung and in the tumor area. These differences are not always in DVH of the lung, although the Wilcoxon test indicated significant differences in 2 of 4 patients. Disagreement in the lung region was also found when the {Gamma} analysis was performed. The effect on TCP is less important than for NTCP because of the slope of the curve at the level of the dose of interest. The effect of dose calculation inaccuracy is patient-dependent and strongly related to beam geometry and to the localization of the tumor. When multiple intensity-modulated beams are used, the effect of the presence of the heterogeneity on dose distribution may not always be easily predictable.

Pasciuti, Katia, E-mail: ka.pasciuti@libero.i [Laboratory of Medical Physics, Istituto Regina Elena, Roma (Italy); Iaccarino, Giuseppe; Strigari, Lidia [Laboratory of Medical Physics, Istituto Regina Elena, Roma (Italy); Malatesta, Tiziana [Medical Physics Department, S. Giovanni Calibita, Fatebenefratelli Hospital, Roma (Italy); Benassi, Marcello; Di Nallo, Anna Maria [Laboratory of Medical Physics, Istituto Regina Elena, Roma (Italy); Mirri, Alessandra; Pinzi, Valentina [Division of Radiotherapy, Istituto Regina Elena, Roma (Italy); Landoni, Valeria [Laboratory of Medical Physics, Istituto Regina Elena, Roma (Italy)

2011-07-01T23:59:59.000Z

296

Efficient Execution of Electronic Structure Calculations on SMP Clusters  

SciTech Connect (OSTI)

Applications augmented with adaptive capabilities are becoming common in parallel computing environments. For large-scale scientific applications, dynamic adjustments to a computationally-intensive part may lead to a large pay-off in facilitating efficient execution of the entire application while aiming at avoiding resource contention. Application-specific knowledge, often best revealed during the run-time, is required to initiate and time these adjustments. In particular, General Atomic and Molecular Electronic Structure System (GAMESS) is a program for ab initio quantum chemistry that places significant demands on the high-performance computing platforms. Certain electronic structure calculations are characterized by high consumption of a particular resource, such as CPU, main memory, or disk I/O. This may lead to resource contention among concurrent GAMESS jobs and other programs in the dynamically changing environment. Thus, it is desirable to improve GAMESS calculations by means of dynamic adaptations. In this thesis, we show how an application- or algorithm-specific knowledge may play a significant role in achieving this goal. The choice of implementation is facilitated by a module-driven middleware easily integrated with GAMESS that assesses resource consumption and invokes GAMESS adaptations to the system environment. We show that the throughput of GAMESS jobs may be improved greatly as a result of such adaptations.

Nurzhan Ustemirov

2006-05-01T23:59:59.000Z

297

Exposure Time Calculator for Immersion Grating Infrared Spectrograph: IGRINS  

E-Print Network [OSTI]

We present an exposure-time calculator (ETC) for the Immersion Grating Infrared Spectrograph (IGRINS). The signal and noise values are calculated by taking into account the telluric background emission and absorption, the emission and transmission of the telescope and instrument optics, and the dark current and read noise of the infrared detector arrays. For the atmospheric transmission, we apply models based on the amount of precipitable water vapor along the line of sight to the target. The ETC produces the expected signal-to-noise ratio (S/N) for each resolution element, given the exposure-time and number of exposures. In this paper, we compare the simulated continuum S/N for the early-type star HD 124683 and the late-type star GSS 32, and the simulated emission line S/N for the H2 rovibrational transitions from the Iris Nebula NGC 7023 with the observed IGRINS spectra. The simulated S/N from the ETC is overestimate by 10 - 15 % for the sample continuum targets.

Le, Huynh Anh N; Jaffe, Daniel T; Lee, Jae-Joon; Im, Myungshin; Kaplan, Kyle; Seifahrt, Andreas

2015-01-01T23:59:59.000Z

298

Measurement and numerical calculation of Rubidium Rydberg Stark spectra  

E-Print Network [OSTI]

We report on the measurement of Stark shifted energy levels of $^{87}$Rb Rydberg atoms in static electric fields by means of electromagnetically induced transparency (EIT). Electric field strengths of up to 500V/cm, ranging beyond the classical ionisation threshold, were applied using electrodes inside a glass cell with rubidium vapour. Stark maps for principal quantum numbers $n=35$ and $n=70$ have been obtained with high signal-to-noise ratio for comparison with results from ab initio calculations following the method described in [M. L. Zimmerman et al., Phys. Rev. A 20, 2251 (1979)], which was originally only verified for states around $n=15$. We also calculate the dipole matrix elements between low-lying states and Stark shifted Rydberg states to give a theoretical estimate of the relative strength of the EIT signal. The present work significantly extends the experimental verification of this numerical method in the range of both high principal quantum numbers and high electric fields with an accuracy of...

Grimmel, Jens; Karlewski, Florian; Jessen, Florian; Reinschmidt, Malte; Sándor, Nóra; Fortágh, József

2015-01-01T23:59:59.000Z

299

Improve Claus simulation by integrating kinetic limitations into equilibrium calculations  

SciTech Connect (OSTI)

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.

Wen, T.C.

1986-01-01T23:59:59.000Z

300

Mass Insertions vs. Mass Eigenstates calculations in Flavour Physics  

E-Print Network [OSTI]

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...

Dedes, A; Rosiek, J; Suxho, K; Tamvakis, K

2015-01-01T23:59:59.000Z

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


301

Recent Developments in No-Core Shell-Model Calculations  

SciTech Connect (OSTI)

We present an overview of recent results and developments of the no-core shell model (NCSM), an ab initio approach to the nuclear many-body problem for light nuclei. In this aproach, we start from realistic two-nucleon or two- plus three-nucleon interactions. Many-body calculations are performed using a finite harmonic-oscillator (HO) basis. To facilitate convergence for realistic inter-nucleon interactions that generate strong short-range correlations, we derive effective interactions by unitary transformations that are tailored to the HO basis truncation. For soft realistic interactions this might not be necessary. If that is the case, the NCSM calculations are variational. In either case, the ab initio NCSM preserves translational invariance of the nuclear many-body problem. In this review, we, in particular, highlight results obtained with the chiral two- plus three-nucleon interactions. We discuss efforts to extend the applicability of the NCSM to heavier nuclei and larger model spaces using importance-truncation schemes and/or use of effective interactions with a core. We outline an extension of the ab initio NCSM to the description of nuclear reactions by the resonating group method technique. A future direction of the approach, the ab initio NCSM with continuum, which will provide a complete description of nuclei as open systems with coupling of bound and continuum states is given in the concluding part of the review.

Navratil, P; Quaglioni, S; Stetcu, I; Barrett, B R

2009-03-20T23:59:59.000Z

302

Monte Carlo calculation of helical tomotherapy dose delivery  

SciTech Connect (OSTI)

Helical tomotherapy delivers intensity modulated radiation therapy using a binary multileaf collimator (MLC) to modulate a fan beam of radiation. This delivery occurs while the linac gantry and treatment couch are both in constant motion, so the beam describes, from a patient/phantom perspective, a spiral or helix of dose. The planning system models this continuous delivery as a large number (51) of discrete gantry positions per rotation, and given the small jaw/fan width setting typically used (1 or 2.5 cm) and the number of overlapping rotations used to cover the target (pitch often <0.5), the treatment planning system (TPS) potentially employs a very large number of static beam directions and leaf opening configurations to model the modulated fields. All dose calculations performed by the system employ a convolution/superposition model. In this work the authors perform a full Monte Carlo (MC) dose calculation of tomotherapy deliveries to phantom computed tomography (CT) data sets to verify the TPS calculations. All MC calculations are performed with the EGSnrc-based MC simulation codes, BEAMnrc and DOSXYZnrc. Simulations are performed by taking the sinogram (leaf opening versus time) of the treatment plan and decomposing it into 51 different projections per rotation, as does the TPS, each of which is segmented further into multiple MLC opening configurations, each with different weights that correspond to leaf opening times. Then the projection is simulated by the summing of all of the opening configurations, and the overall rotational treatment is simulated by the summing of all of the projection simulations. Commissioning of the source model was verified by comparing measured and simulated values for the percent depth dose and beam profiles shapes for various jaw settings. The accuracy of the MLC leaf width and tongue and groove spacing were verified by comparing measured and simulated values for the MLC leakage and a picket fence pattern. The validated source and MLC configuration were then used to simulate a complex modulated delivery from fixed gantry angle. Further, a preliminary rotational treatment plan to a delivery quality assurance phantom (the 'cheese' phantom) CT data set was simulated. Simulations were compared with measured results taken with an A1SL ionization chamber or EDR2 film measurements in a water tank or in a solid water phantom, respectively. The source and MLC MC simulations agree with the film measurements, with an acceptable number of pixels passing the 2%/1 mm gamma criterion. 99.8% of voxels of the MC calculation in the planning target volume (PTV) of the preliminary plan passed the 2%/2 mm gamma value test. 87.0% and 66.2% of the voxels in two organs at risk (OARs) passed the 2%/2 mm tests. For a 3%/3 mm criterion, the PTV and OARs show 100%, 93.2%, and 86.6% agreement, respectively. All voxels passed the gamma value test with a criterion of 5%/3 mm. The TomoTherapy TPS showed comparable results.

Zhao Yingli; Mackenzie, M.; Kirkby, C.; Fallone, B. G. [Department of Medical Physics, Cross Cancer Institute, University of Alberta, 11560 University Avenue, Edmonton, Alberta T6G 1Z2 (Canada) and Department of Physics, University of Alberta, 11560 University Avenue, Edmonton, Alberta T6G 1Z2 (Canada); Department of Medical Physics, Cross Cancer Institute, 11560 University Avenue, Edmonton, Alberta T6G 1Z2 (Canada); Department of Medical Physics, Cross Cancer Institute, University of Alberta, 11560 University Avenue, Edmonton, Alberta T6G 1Z2, Canada and Department of Physics, University of Alberta, 11560 University Avenue, Edmonton, Alberta T6G 1Z2 (Canada)

2008-08-15T23:59:59.000Z

303

Modularization and simulation techniques for heat balance-based energy and load calculation  

E-Print Network [OSTI]

the Loads Toolkit research project is to obtain a heat balance based load calculation procedure that

Richard K. Strand

2001-01-01T23:59:59.000Z

304

NUMERICAL CALCULATIONS FOR THE ASYMPTOTIC, DIFFUSION DOMINATED MASS-TRANSFER COEFFICIENT IN PACKED BED REACTORS  

E-Print Network [OSTI]

Calculations for the Asymptotic, Diffusion Dominated Mass-Transfer Coefficient in Packed Bed Reactors

Fedkiw, Peter

2011-01-01T23:59:59.000Z

305

CLEAR (Calculates Logical Evacuation And Response): A Generic Transportation Network Model for the Calculation of Evacuation Time Estimates  

SciTech Connect (OSTI)

This paper describes the methodology and application of the computer model CLEAR (Calculates Logical Evacuation And Response) which estimates the time required for a specific population density and distribution to evacuate an area using a specific transportation network. The CLEAR model simulates vehicle departure and movement on a transportation network according to the conditions and consequences of traffic flow. These include handling vehicles at intersecting road segments, calculating the velocity of travel on a road segment as a function of its vehicle density, and accounting for the delay of vehicles in traffic queues. The program also models the distribution of times required by individuals to prepare for an evacuation. In order to test its accuracy, the CLEAR model was used to estimate evacuatlon tlmes for the emergency planning zone surrounding the Beaver Valley Nuclear Power Plant. The Beaver Valley site was selected because evacuation time estimates had previously been prepared by the licensee, Duquesne Light, as well as by the Federal Emergency Management Agency and the Pennsylvania Emergency Management Agency. A lack of documentation prevented a detailed comparison of the estimates based on the CLEAR model and those obtained by Duquesne Light. However, the CLEAR model results compared favorably with the estimates prepared by the other two agencies.

Moeller, M. P.; Urbanik, II, T.; Desrosiers, A. E.

1982-03-01T23:59:59.000Z

306

Refinements in Effective Potential Calculations in the MSSM  

E-Print Network [OSTI]

The one-loop effective potential is a powerful tool in studying the electroweak symmetry breaking of supersymmetric theories, whose precise calculation may have important phenomenological consequences. In this work, we are correctly treating the contribution of the Higgs sector to the effective potential and refine the radiative corrections to the Higgs mixing parameter $\\mu$, which is known to affect greatly the supersymmetric spectrum. Working at the average stop scale to minimize the effect of the stop sector, we find additional corrections which can play a dominant role in the Focus Point region of the parameter space of the MSSM. The comparison of our results with those of the literature is discussed. We also discuss the gauge dependence of the effective potential and its effect on the $\\mu$ parameter in analyses where this is determined from the 1-loop minimization conditions of the effective potential.

M. Argyrou; A. Katsikatsou; I. Malamos

2006-02-17T23:59:59.000Z

307

Center of pressure calculations for a bent-axis vehicle  

SciTech Connect (OSTI)

Bent-axis maneuvering vehicles provide a unique type of control for a variety of supersonic and hypersonic missions. Unfortunately, large hinge moments, incomplete pitching moment predictions, and a misunderstanding of corresponding center of pressure calculations have prevented their application. A procedure is presented for the efficient design of bent-axis vehicles given an adequate understanding of origins of pitching moment effects. In particular,sources of pitching moment contributions will be described including not only normal force, but inviscid axial force and viscous effects as well. Off-centerline center of pressure effects are first reviewed for symmetric hypersonic sphere-cone configurations. Next the effects of the bent-axis geometry are considered where axial force, acting on the deflected tail section, can generate significant pitching moment components. The unique relationship between hinge moments and pitching moments for the bent-axis class of vehicles is discussed. 15 refs.

Rutledge, W.H.; Polansky, G.F.

1992-01-01T23:59:59.000Z

308

Novel variational approach for photonic crystal slab mode calculation  

E-Print Network [OSTI]

We propose a new method based on variational principle for analysis of photonic crystal (PC) slabs. Most of the methods used today treat PC slab as a three-dimensional (3D) crystal and this makes them very time and/or memory consuming. In this method we use Bloch theorem to expand the field on infinite plane waves which their amplitudes depend on the component perpendicular to the slab surface. By approximating these amplitudes with appropriate functions, we can find modes of PC slabs almost as fast as we can find modes of a two-dimensional (2D) crystal. Besides this advantage, we can also calculate radiation modes with this method which is not feasible with 3D Plane Wave Expansion (PWE) method.

Aram, Mohammad Hasan

2015-01-01T23:59:59.000Z

309

Calculation of TMD Evolution for Transverse Single Spin Asymmetry Measurements  

SciTech Connect (OSTI)

In this letter, we show that it is necessary to include the full treatment of QCD evolution of Transverse Momentum Dependent parton densities to explain discrepancies between HERMES data and recent COMPASS data on a proton target for the Sivers transverse single spin asymmetry in Semi-Inclusive Deep Inelastic Scattering (SIDIS). Calculations based on existing fits to TMDs in SIDIS, and including evolution within the Collins-Soper-Sterman with properly defined TMD PDFs are shown to provide a good explanation for the discrepancy. The non-perturbative input needed for the implementation of evolution is taken from earlier analyses of unpolarized Drell-Yan (DY) scattering at high energy. Its success in describing the Sivers function in SIDIS data at much lower energies is strong evidence in support of the unifying aspect of the QCD TMD-factorization formalism.

Mert Aybat, Ted Rogers, Alexey Prokudin

2012-06-01T23:59:59.000Z

310

Calculating the chiral condensate diagrammatically at strong coupling  

E-Print Network [OSTI]

We calculate the chiral condensate of QCD at infinite coupling as a function of the number of fundamental fermion flavours using a lattice diagrammatic approach inspired by recent work of Tomboulis, and other work from the 80's. We outline the approach where the diagrams are formed by combining a truncated number of sub-diagram types in all possible ways. Our results show evidence of convergence and agreement with simulation results at small Nf. However, contrary to recent simulation results, we do not observe a transition at a critical value of Nf. We further present preliminary results for the chiral condensate of QCD with symmetric or adjoint representation fermions at infinite coupling as a function of Nf for Nc = 3. In general, there are sources of error in this approach associated with miscounting of overlapping diagrams, and over-counting of diagrams due to symmetries. These are further elaborated upon in a longer paper.

Christensen, Alexander S; Pedersen, Peter D; Rosseel, Jan

2015-01-01T23:59:59.000Z

311

Hanford Apatite Treatability Test Report Errata: Apatite Mass Loading Calculation  

SciTech Connect (OSTI)

The objective of this errata report is to document an error in the apatite loading (i.e., treatment capacity) estimate reported in previous apatite treatability test reports and provide additional calculation details for estimating apatite loading and barrier longevity. The apatite treatability test final report (PNNL-19572; Vermeul et al. 2010) documents the results of the first field-scale evaluation of the injectable apatite PRB technology. The apatite loading value in units of milligram-apatite per gram-sediment is incorrect in this and some other previous reports. The apatite loading in units of milligram phosphate per gram-sediment, however, is correct, and this is the unit used for comparison to field core sample measurements.

Szecsody, James E.; Vermeul, Vincent R.; Williams, Mark D.; Truex, Michael J.

2014-05-19T23:59:59.000Z

312

Calculations on permanent-magnet quadrupoles with nonrectangular cross section  

SciTech Connect (OSTI)

The current trend toward higher frequencies to power drift-tube linacs (DTLs) and coupled-cavity linacs (CCLs) reduces the space available for quadrupole focusing magnets. Similarly, the space available for matching sections between linac sections is limited, and often the matching section bunchers are designed in odd shapes to make them fit. This shaping further restricts focusing magnet space. One approach to attaining sufficient quadrupole strength is such situations is to use rare-earth permanent-magnet quadrupoles (PMQs) with cross sections tailored to fill as much of the available space as possible. In this paper, we describe some techniques we have developed to calculate the properties of such magnets both singly and when other magnets are nearby. 3 refs., 4 figs.

Boicourt, G.P.; Merson, J.L.

1988-01-01T23:59:59.000Z

313

Fast calculation of HELAS amplitudes using graphics processing unit (GPU)  

E-Print Network [OSTI]

We use the graphics processing unit (GPU) for fast calculations of helicity amplitudes of physics processes. As our first attempt, we compute $u\\bar{u}\\to n\\gamma$ ($n=2$ to 8) processes in $pp$ collisions at $\\sqrt{s} = 14$TeV by transferring the MadGraph generated HELAS amplitudes (FORTRAN) into newly developed HEGET ({\\bf H}ELAS {\\bf E}valuation with {\\bf G}PU {\\bf E}nhanced {\\bf T}echnology) codes written in CUDA, a C-platform developed by NVIDIA for general purpose computing on the GPU. Compared with the usual CPU programs, we obtain 40-150 times better performance on the GPU.

K. Hagiwara; J. Kanzaki; N. Okamura; D. Rainwater; T. Stelzer

2010-10-11T23:59:59.000Z

314

Uncertainty Quantification of Calculated Temperatures for the AGR-1 Experiment  

SciTech Connect (OSTI)

This report documents an effort to quantify the uncertainty of the calculated temperature data for the first Advanced Gas Reactor (AGR-1) fuel irradiation experiment conducted in the INL’s Advanced Test Reactor (ATR) in support of the Next Generation Nuclear Plant (NGNP) R&D program. Recognizing uncertainties inherent in physics and thermal simulations of the AGR-1 test, the results of the numerical simulations can be used in combination with the statistical analysis methods to improve qualification of measured data. Additionally, the temperature simulation data for AGR tests can be used for validation of the fuel transport and fuel performance simulation models. The crucial roles of the calculated fuel temperatures in ensuring achievement of the AGR experimental program objectives require accurate determination of the model temperature uncertainties. The report is organized into three chapters. Chapter 1 introduces the AGR Fuel Development and Qualification program and provides overviews of AGR-1 measured data, AGR-1 test configuration and test procedure, and thermal simulation. Chapters 2 describes the uncertainty quantification procedure for temperature simulation data of the AGR-1 experiment, namely, (i) identify and quantify uncertainty sources; (ii) perform sensitivity analysis for several thermal test conditions; (iii) use uncertainty propagation to quantify overall response temperature uncertainty. A set of issues associated with modeling uncertainties resulting from the expert assessments are identified. This also includes the experimental design to estimate the main effects and interactions of the important thermal model parameters. Chapter 3 presents the overall uncertainty results for the six AGR-1 capsules. This includes uncertainties for the daily volume-average and peak fuel temperatures, daily average temperatures at TC locations, and time-average volume-average and time-average peak fuel temperatures.

Binh T. Pham; Jeffrey J. Einerson; Grant L. Hawkes

2013-03-01T23:59:59.000Z

315

MONTE-CARLO BURNUP CALCULATION UNCERTAINTY QUANTIFICATION AND PROPAGATION DETERMINATION  

SciTech Connect (OSTI)

MONTEBURNS is a Monte-Carlo depletion routine utilizing MCNP and ORIGEN 2.2. Uncertainties exist in the MCNP transport calculation, but this information is not passed to the depletion calculation in ORIGEN or saved. To quantify this transport uncertainty and determine how it propagates between burnup steps, a statistical analysis of a multiple repeated depletion runs is performed. The reactor model chosen is the Oak Ridge Research Reactor (ORR) in a single assembly, infinite lattice configuration. This model was burned for a 25.5 day cycle broken down into three steps. The output isotopics as well as effective multiplication factor (k-effective) were tabulated and histograms were created at each burnup step using the Scott Method to determine the bin width. It was expected that the gram quantities and k-effective histograms would produce normally distributed results since they were produced from a Monte-Carlo routine, but some of results do not. The standard deviation at each burnup step was consistent between fission product isotopes as expected, while the uranium isotopes created some unique results. The variation in the quantity of uranium was small enough that, from the reaction rate MCNP tally, round off error occurred producing a set of repeated results with slight variation. Statistical analyses were performed using the {chi}{sup 2} test against a normal distribution for several isotopes and the k-effective results. While the isotopes failed to reject the null hypothesis of being normally distributed, the {chi}{sup 2} statistic grew through the steps in the k-effective test. The null hypothesis was rejected in the later steps. These results suggest, for a high accuracy solution, MCNP cell material quantities less than 100 grams and greater kcode parameters are needed to minimize uncertainty propagation and minimize round off effects.

Nichols, T.; Sternat, M.; Charlton, W.

2011-05-08T23:59:59.000Z

316

Uncertainty Quantification of Calculated Temperatures for the AGR-1 Experiment  

SciTech Connect (OSTI)

This report documents an effort to quantify the uncertainty of the calculated temperature data for the first Advanced Gas Reactor (AGR-1) fuel irradiation experiment conducted in the INL's Advanced Test Reactor (ATR) in support of the Next Generation Nuclear Plant (NGNP) R&D program. Recognizing uncertainties inherent in physics and thermal simulations of the AGR-1 test, the results of the numerical simulations can be used in combination with the statistical analysis methods to improve qualification of measured data. Additionally, the temperature simulation data for AGR tests can be used for validation of the fuel transport and fuel performance simulation models. The crucial roles of the calculated fuel temperatures in ensuring achievement of the AGR experimental program objectives require accurate determination of the model temperature uncertainties. The report is organized into three chapters. Chapter 1 introduces the AGR Fuel Development and Qualification program and provides overviews of AGR-1 measured data, AGR-1 test configuration and test procedure, and thermal simulation. Chapters 2 describes the uncertainty quantification procedure for temperature simulation data of the AGR-1 experiment, namely, (i) identify and quantify uncertainty sources; (ii) perform sensitivity analysis for several thermal test conditions; (iii) use uncertainty propagation to quantify overall response temperature uncertainty. A set of issues associated with modeling uncertainties resulting from the expert assessments are identified. This also includes the experimental design to estimate the main effects and interactions of the important thermal model parameters. Chapter 3 presents the overall uncertainty results for the six AGR-1 capsules. This includes uncertainties for the daily volume-average and peak fuel temperatures, daily average temperatures at TC locations, and time-average volume-average and time-average peak fuel temperatures.

Binh T. Pham; Jeffrey J. Einerson; Grant L. Hawkes

2012-04-01T23:59:59.000Z

317

Calculating limits for torsion and tensile loads on drill pipe  

SciTech Connect (OSTI)

Drill pipe used for drilling horizontal and extended reach holes experiences much higher torsional and tensile loads than normally seen while drilling vertical holes. This is particularly true for rigs with top drives vs. rigs with rotary tables. When pipe is rotated while pulling out of the hole, which is commonly done on top drive rigs, the drill pipe can experience high tensile and torsional loading simultaneously. These conditions increase the probability of overload on tool joints and require that the drill pipe and tool joint selection process include consideration of combined loading. Calculating the required drill pipe strength for vertical holes is straightforward and spelled out in Section 5 of API RP7G. In vertical hole applications, pipe is almost always selected for its tensile capacity and the torsional strength of the pipe generally does not require special consideration. In Section 4 of API Sec 7, API recommends that the tool joints have a torsional strength of 80% of the pipe`s torsional strength; this is usually adequate. The torsional strength and tensile strength of commonly used drill pipe and tool joint combinations are tabulated in Tables 2 through 10 of API RP7G. Appendix A.8.3 in API RP7G shows a method for plotting a graphical representation of the combined torsional and tensile operational limits of tool joints. How to calculate the limits of the drill pipe tube is shown in Appendix A.9.2. This paper defines terms and limits, and discusses building and using a diagram to determine safe loads.

Bailey, E.I. [Stress Engineering Service Inc., Houston, TX (United States); Smith, J.E. [Grant Prideco, Houston, TX (United States)

1998-02-01T23:59:59.000Z

318

Scoping Inventory Calculations for the Rare Isotope Accelerator  

SciTech Connect (OSTI)

This document is a report on our activities in FY03 exploring nuclear safety and hazard analysis issues relevant to the Rare Isotope Accelerator (RIA). It is not clear whether DOE will classify the RIA as an accelerator facility subject to the accelerator-specific safety requirements of DOE Order 420.2A or as a nonreactor nuclear facility subject to the requirements of 10 CFR 830. The final outcome of this issue will have significant impact on the construction and operation of the facility and the quality assurance requirements for items or services that may affect nuclear safety. The resolution of this issue will be an important earlier decision for the RIA project team and will require early consultation with the appropriate DOE authorities. For nuclear facilities, facility hazard classification depends on the inventory of releasable radionuclides; therefore, some simplistic, scoping inventory calculations for some assumed targets and beams are done to estimate the hazard category of RIA if it is declared a nuclear facility. These calculations show that for the scenarios analyzed, RIA would produce sufficient quantities of radionuclides to be classified as a Category 3 nuclear facility. Over the lifetime of RIA operations, it may be possible to build up Category 2 quantities of {sup 227}Ac and {sup 228}Th. A storage building, separate from the driver, target, and experimental buildings, used to store and isolate accumulated targets and other hardware, can mitigate the potential impact on RIA. The more onerous requirements of Category 2 facilities would only be imposed on the storage facility and not on the rest of the RIA facilities. Some of the differences in a category 2 and category 3 facility are discussed in Appendix 1.

Ahle, L E; Boles, J L

2003-07-25T23:59:59.000Z

319

User's manual for GILDA: An infinite lattice diffusion theory calculation  

SciTech Connect (OSTI)

GILDA is a static two-dimensional diffusion theory code that performs either buckling (B[sup 2]) or k-effective (k[sub eff]) calculations for an infinite hexagonal lattice which is constructed by repeating identical seven-cell zones (one cell is one or seven identical homogenized hexes). GILDA was written by J. W. Stewart in 1973. This user's manual is intended to provide all of the information necessary to set up and execute a GILDA calculation and to interpret the output results. It is assumed that the user is familiar with the computer (VAX/VMS or IBM/MVS) and the JOSHUA system database on which the code is implemented. Users who are not familiar with the JOSHUA database are advised to consult additional references to understand the structure of JOSHUA records and data sets before turning to section 4 of this manual. Sections 2 and 3 of this manual serve as a theory document in which the basic diffusion theory and the numerical approximations behind the code are described. Section 4 describes the functions of the program's subroutines. Section 5 describes the input data and tutors the user how to set up a problem. Section 6 describes the output results and the error messages which may be encountered during execution. Users who only wish to learn how to run the code without understanding the theory can start from section 4 and use sections 2 and 3 as references. Finally, the VAX/VMS and the IBM execution command files together with sample input records are provided in the appendices at the end of this manual.

Le, T.T.

1991-11-01T23:59:59.000Z

320

als double-crystal monochromator: Topics by E-print Network  

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

newest additions to Sony's Bsec. for compatibility with slower vision systems using Sony XC-55 cameras. The XC-HR50 and XC-HR70 cameras incorporate Demoulin, Pascal 20 Stress...

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


321

E-Print Network 3.0 - artificial channel-cut monochromator Sample...  

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

Physics 20 INFLUENCE OF QUANTUM-DOTS DENSITY ON AVERAGE IN-PLANE STRAIN OF OPTOELECTRONIC DEVICES Summary: detector channel-cut Ge220 analyser sample X-ray tube point focus...

322

E-Print Network 3.0 - acceptance crystal monochromator Sample...  

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

... Source: Controlled Fusion Atomic Data Center (CFADC) Collection: Plasma Physics and Fusion 13 MACS -A New High Intensity Cold Neutron Spectrometer at NIST Summary: V (Ei2.1...

323

Thermal and mechanical joints to cryo-cooled silicon monochromator crystals  

E-Print Network [OSTI]

resistance of the joint. The operating temperature of –150 ooperating temperature range was as small as possible in an attempt to reduce the strain in the joint and

MacDowell, A.; Fakra, S.; Morrison, G.

2006-01-01T23:59:59.000Z

324

Periodic magnetic fieldas a polarized and focusing thermal neutron spectrometer and monochromator  

E-Print Network [OSTI]

B828?. The aluminum spacers had dimensions 12.7 ? 2.54? 12.7magnet pole dimension ?axial width? Aluminum spacer width

2010-01-01T23:59:59.000Z

325

ANL/APS/TB-24 Diamond Monochromators for APS Undulator-A Beamlines  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered‰PNGExperience4AJ01) (See95TI07)Operations2 Print258Department of31 . Wiggler9 A4

326

Density Functional Theory Calculations of Mass Transport in UO2  

SciTech Connect (OSTI)

In this talk we present results of density functional theory (DFT) calculations of U, O and fission gas diffusion in UO{sub 2}. These processes all impact nuclear fuel performance. For example, the formation and retention of fission gas bubbles induce fuel swelling, which leads to mechanical interaction with the clad thereby increasing the probability for clad breach. Alternatively, fission gas can be released from the fuel to the plenum, which increases the pressure on the clad walls and decreases the gap thermal conductivity. The evolution of fuel microstructure features is strongly coupled to diffusion of U vacancies. Since both U and fission gas transport rates vary strongly with the O stoichiometry, it is also important to understand O diffusion. In order to better understand bulk Xe behavior in UO{sub 2{+-}x} we first calculate the relevant activation energies using DFT techniques. By analyzing a combination of Xe solution thermodynamics, migration barriers and the interaction of dissolved Xe atoms with U, we demonstrate that Xe diffusion predominantly occurs via a vacancy-mediated mechanism. Since Xe transport is closely related to diffusion of U vacancies, we have also studied the activation energy for this process. In order to explain the low value of 2.4 eV found for U migration from independent damage experiments (not thermal equilibrium) the presence of vacancy clusters must be included in the analysis. Next we investigate species transport on the (111) UO{sub 2} surface, which is motivated by the formation of small voids partially filled with fission gas atoms (bubbles) in UO{sub 2} under irradiation. Surface diffusion could be the rate-limiting step for diffusion of such bubbles, which is an alternative mechanism for mass transport in these materials. As expected, the activation energy for surface diffusion is significantly lower than for bulk transport. These results are further discussed in terms of engineering-scale fission gas release models. Finally, oxidation of UO{sub 2} and the importance of cluster formation for understanding thermodynamic and kinetic properties of UO{sub 2+x} are investigated.

Andersson, Anders D. [Los Alamos National Laboratory; Dorado, Boris [CEA; Uberuaga, Blas P. [Los Alamos National Laboratory; Stanek, Christopher R. [Los Alamos National Laboratory

2012-06-26T23:59:59.000Z

327

Hyperon Puzzle: Hints from Quantum Monte Carlo Calculations  

E-Print Network [OSTI]

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.

Diego Lonardoni; Alessandro Lovato; Stefano Gandolfi; Francesco Pederiva

2015-02-27T23:59:59.000Z

328

The status of nuclear data for transmutation calculations  

SciTech Connect (OSTI)

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.

Wilson, W.B.; England, T.R.; MacFarlane, R.E.; Muir, D.W.; Young, P.G.

1995-12-01T23:59:59.000Z

329

Efficient Error Calculation for Multiresolution Texture-Based Volume Visualization  

SciTech Connect (OSTI)

Multiresolution texture-based volume visualization is an excellent technique to enable interactive rendering of massive data sets. Interactive manipulation of a transfer function is necessary for proper exploration of a data set. However, multiresolution techniques require assessing the accuracy of the resulting images, and re-computing the error after each change in a transfer function is very expensive. They extend their existing multiresolution volume visualization method by introducing a method for accelerating error calculations for multiresolution volume approximations. Computing the error for an approximation requires adding individual error terms. One error value must be computed once for each original voxel and its corresponding approximating voxel. For byte data, i.e., data sets where integer function values between 0 and 255 are given, they observe that the set of error pairs can be quite large, yet the set of unique error pairs is small. instead of evaluating the error function for each original voxel, they construct a table of the unique combinations and the number of their occurrences. To evaluate the error, they add the products of the error function for each unique error pair and the frequency of each error pair. This approach dramatically reduces the amount of computation time involved and allows them to re-compute the error associated with a new transfer function quickly.

LaMar, E; Hamann, B; Joy, K I

2001-10-16T23:59:59.000Z

330

Calculating the probability of injected carbon dioxide plumes encountering faults  

SciTech Connect (OSTI)

One of the main concerns of storage in saline aquifers is leakage via faults. In the early stages of site selection, site-specific fault coverages are often not available for these aquifers. This necessitates a method using available fault data to estimate the probability of injected carbon dioxide encountering and migrating up a fault. The probability of encounter can be calculated from areal fault density statistics from available data, and carbon dioxide plume dimensions from numerical simulation. Given a number of assumptions, the dimension of the plume perpendicular to a fault times the areal density of faults with offsets greater than some threshold of interest provides probability of the plume encountering such a fault. Application of this result to a previously planned large-scale pilot injection in the southern portion of the San Joaquin Basin yielded a 3% and 7% chance of the plume encountering a fully and half seal offsetting fault, respectively. Subsequently available data indicated a half seal-offsetting fault at a distance from the injection well that implied a 20% probability of encounter for a plume sufficiently large to reach it.

Jordan, P.D.

2011-04-01T23:59:59.000Z

331

Development of nuclear models for higher energy calculations  

SciTech Connect (OSTI)

Two nuclear models for higher energy calculations have been developed in the regions of high and low energy transfer, respectively. In the former, a relativistic hybrid-type preequilibrium model is compared with data ranging from 60 to 800 MeV. Also, the GNASH exciton preequilibrium-model code with higher energy improvements is compared with data at 200 and 318 MeV. In the region of low energy transfer, nucleon-nucleus scattering is predominately a direct reaction involving quasi-elastic collisions with one or more target nucleons. We discuss various aspects of quasi-elastic scattering which are important in understanding features of cross sections and spin observables. These include (1) contributions from multi-step processes; (2) damping of the continuum response from 2p-2h excitations; (3) the ''optimal'' choice of frame in which to evaluate the nucleon-nucleon amplitudes; and (4) the effect of optical and spin-orbit distortions, which are included in a model based on the RPA the DWIA and the eikonal approximation. 33 refs., 15 figs.

Bozoian, M.; Siciliano, E.R.; Smith, R.D.

1988-01-01T23:59:59.000Z

332

Calculation of Helium nuclei in quenched lattice QCD  

E-Print Network [OSTI]

We present results for the binding energies for ^4He and ^3He nuclei calculated in quenched lattice QCD at the lattice spacing of a =0.128 fm with a heavy quark mass corresponding to m_pi = 0.8 GeV. Enormous computational cost for the nucleus correlation functions is reduced by avoiding redundancy of equivalent contractions stemming from permutation symmetry of protons or neutrons in the nucleus and various other symmetries. To distinguish a bound state from an attractive scattering state, we investigate the volume dependence of the energy difference between the ground state energy of the nucleus channel and the free multi-nucleon states by changing the spatial extent of the lattice from 3.1 fm to 12.3 fm. A finite energy difference left in the infinite spatial volume limit leads to the conclusion that the measured ground states are bounded. It is also encouraging that the measured binding energies and the experimental ones show the same order of magnitude.

T. Yamazaki

2010-12-02T23:59:59.000Z

333

WIPP Compliance Certification Application calculations parameters. Part 1: Parameter development  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) in southeast New Mexico has been studied as a transuranic waste repository for the past 23 years. During this time, an extensive site characterization, design, construction, and experimental program was completed, which provided in-depth understanding of the dominant processes that are most likely to influence the containment of radionuclides for 10,000 years. Nearly 1,500 parameters were developed using information gathered from this program; the parameters were input to numerical models for WIPP Compliance Certification Application (CCA) Performance Assessment (PA) calculations. The CCA probabilistic codes frequently require input values that define a statistical distribution for each parameter. Developing parameter distributions begins with the assignment of an appropriate distribution type, which is dependent on the type, magnitude, and volume of data or information available. The development of the parameter distribution values may require interpretation or statistical analysis of raw data, combining raw data with literature values, scaling of lab or field data to fit code grid mesh sizes, or other transformation. Parameter development and documentation of the development process were very complicated, especially for those parameters based on empirical data; they required the integration of information from Sandia National Laboratories (SNL) code sponsors, parameter task leaders (PTLs), performance assessment analysts (PAAs), and experimental principal investigators (PIs). This paper, Part 1 of two parts, contains a discussion of the parameter development process, roles and responsibilities, and lessons learned. Part 2 will discuss parameter documentation, traceability and retrievability, and lessons learned from related audits and reviews.

Howarth, S.M.

1997-11-14T23:59:59.000Z

334

Calculation of Reactive-evaporation Rates of Chromia  

SciTech Connect (OSTI)

A methodology is developed to calculate Cr-evaporation rates from Cr2O3 with a flat planar geometry. Variables include temperature, total pressure, gas velocity, and gas composition. The methodology was applied to solid-oxide, fuel cell conditions for metallic interconnects and to advanced-steam turbines conditions. The high velocities and pressures of the advanced steam turbine led to evaporation predictions as high as 5.18 9 10-8 kg/m2/s of CrO2(OH)2(g) at 760 °C and 34.5 MPa. This is equivalent to 0.080 mm per year of solid Cr loss. Chromium evaporation is expected to be an important oxidation mechanism with the types of nickel-base alloys proposed for use above 650 °C in advanced-steam boilers and turbines. It is shown that laboratory experiments, with much lower steam velocities and usually much lower total pressure than found in advanced steam turbines, would best reproduce chromium-evaporation behavior with atmospheres that approach either O2 + H2O or air + H2O with 57% H2O.

Holcomb, G.R.

2008-04-01T23:59:59.000Z

335

Calculating Energy Savings in High Performance Residential Buildings Programs: Preprint  

SciTech Connect (OSTI)

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.

Hendron, B.; Rarrar-Nagy, S.; Anderson, R.; Judkoff, R.; Reeves, P.; Hancock, E.

2003-08-01T23:59:59.000Z

336

SCWR Once-Through Calculations for Transmutation and Cross Sections  

SciTech Connect (OSTI)

It is the purpose of this report to document the calculation of (1) the isotopic evolution and of (2) the 1-group cross sections as a function of burnup of the reference Super Critical Water Reactor (SCWR), in a format suitable for the Fuel Cycle Option Campaign Transmutation Data Library. The reference SCWR design was chosen to be that described in [McDonald, 2005]. Super Critical Water Reactors (SCWR) are intended to operate with super-critical water (i.e. H2O at a pressure above 22 MPa and a temperature above 373oC) as a cooling – and possibly also moderating – fluid. The main mission of the SCWR is to generate lower cost electricity, as compared to current standard Light Water Reactors (LWR). Because of the high operating pressure and temperature, SCWR feature a substantially higher thermal conversion efficiency than standard LWR – i.e. about 45% versus 33%, mostly due to an increase in the exit water temperature from ~300oC to ~500oC – potentially resulting in a lower cost of generated electricity. The coolant remains single phase throughout the reactor and the energy conversion system, thus eliminating the need for pressurizers, steam generators, steam separators and dryers, further potentially reducing the reactor construction capital cost. The SCWR concept presented here is based on existing LWR technology and on a large number of existing fossil-fired supercritical boilers. However, it was concluded in [McDonald, 2005], that: “Based on the results of this study, it appears that the reference SCWR design is not feasible.” This conclusion appears based on the strong sensitivity of the design to small deviations in nominal conditions leading to small effects having a potentially large impact on the peak cladding temperature of some fuel rods. “This was considered a major feasibility issue for the SCWR” [McDonald, 2005]. After a description of the reference SCWR design, the Keno V 3-D single assembly model used for this analysis, as well as the calculated results, are presented. Additionally, the follwing information, presented in the appendixes, is intended to provide enough guidance that a researcher repeating the same task in the future should be able to obtain a vector of nuclei and cross sections ready for insertion into the transmutation library without any need for further instructions: (1) Complete TRITON/KENO-V input used for the analysis; (2) Inputs and detailed description of the usage of the OPUS utility, used to postproces and to extract the nuclei concentrations for the transmutation library; (3) Inputs and detailed description of the usage of the XSECLIST utility, used to postproces and to extract the 1-group cross sections for the transmutation library; (4) Details of an ad-hoc utility program developed to sort the nuclei and cross sections for the transmutation library.

ganda, francesco (090771)

2012-07-01T23:59:59.000Z

337

A Framework for Lattice QCD Calculations on GPUs  

E-Print Network [OSTI]

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.

F. T. Winter; M. A. Clark; R. G. Edwards; B. Joó

2014-08-25T23:59:59.000Z

338

A Framework for Lattice QCD Calculations on GPUs  

SciTech Connect (OSTI)

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.

Winter, Frank; Clark, M.A.; Edwards, Robert G.; Joo, Balint

2014-08-01T23:59:59.000Z

339

Simulated combined abnormal environment fire calculations for aviation impacts.  

SciTech Connect (OSTI)

Aircraft impacts at flight speeds are relevant environments for aircraft safety studies. This type of environment pertains to normal environments such as wildlife impacts and rough landings, but also the abnormal environment that has more recently been evidenced in cases such as the Pentagon and World Trade Center events of September 11, 2001, and the FBI building impact in Austin. For more severe impacts, the environment is combined because it involves not just the structural mechanics, but also the release of the fuel and the subsequent fire. Impacts normally last on the order of milliseconds to seconds, whereas the fire dynamics may last for minutes to hours, or longer. This presents a serious challenge for physical models that employ discrete time stepping to model the dynamics with accuracy. Another challenge is that the capabilities to model the fire and structural impact are seldom found in a common simulation tool. Sandia National Labs maintains two codes under a common architecture that have been used to model the dynamics of aircraft impact and fire scenarios. Only recently have these codes been coupled directly to provide a fire prediction that is better informed on the basis of a detailed structural calculation. To enable this technology, several facilitating models are necessary, as is a methodology for determining and executing the transfer of information from the structural code to the fire code. A methodology has been developed and implemented. Previous test programs at the Sandia National Labs sled track provide unique data for the dynamic response of an aluminum tank of liquid water impacting a barricade at flight speeds. These data are used to validate the modeling effort, and suggest reasonable accuracy for the dispersion of a non-combustible fluid in an impact environment. The capability is also demonstrated with a notional impact of a fuel-filled container at flight speed. Both of these scenarios are used to evaluate numeric approximations, and help provide an understanding of the quantitative accuracy of the modeling methods.

Brown, Alexander L.

2010-08-01T23:59:59.000Z

340

Radionuclide release calculations for selected severe accident scenarios  

SciTech Connect (OSTI)

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

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

1990-08-01T23:59:59.000Z

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


341

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

E-Print Network [OSTI]

Weigel, Southworth, and Meyer 1 Calculators for Estimating Greenhouse Gas Emissions from Public Greenhouse Gas Emissions from Public Transit Agency Vehicle Fleet Operations ABSTRACT This paper reviews calculation tools available for quantifying the greenhouse gas emissions associated with different types

342

Calculation of heat capacities of light and heavy water by path-integral molecular dynamics  

E-Print Network [OSTI]

Calculation of heat capacities of light and heavy water by path-integral molecular dynamics-integral molecular dynamics has been used to calculate the constant-volume heat capacities of light and heavy water

Nielsen, Steven O.

343

A Bin Method for Calculating Energy Conservation Retrofit Savings in Commercial Buildings  

E-Print Network [OSTI]

The calculation of measured energy savings from energy conservation retrofits is an important step in the verification of the success of a retrofit (Claridge et al. 1992). Several methods for calculating the savings from energy conservation...

Thamilseran, S.; Haberl, J. S.

1994-01-01T23:59:59.000Z

344

Calculated corrections to superallowed Fermi beta decay: New evaluation of the nuclear-structure-dependent terms  

E-Print Network [OSTI]

is accurate calculations for the radiative and isospin symmetry-breaking corrections that must be applied to the experimental data. We present a new and consistent set of calculations for the nuclear-structure-dependent components of these corrections...

Towner, IS; Hardy, John C.

2002-01-01T23:59:59.000Z

345

E-Print Network 3.0 - au calcul des Sample Search Results  

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

calcul des Search Powered by Explorit Topic List Advanced Search Sample search results for: au calcul des Page: << < 1 2 3 4 5 > >> 1 Les parties colores correspondent des actions...

346

Historical Survey of Daylighting Calculations Methods and Their Use in Energy Performance Simulations  

E-Print Network [OSTI]

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...

Kota, S.; Haberl, J. S.

347

A general performance model for parallel sweeps on orthogonal grids for particle transport calculations  

E-Print Network [OSTI]

particle transport calculations is an important problem in many applications targeted by the Accelerated Strategic Computing Initiative of the United States Department of Energy. One common approach to deterministic particle transport calculations...

Mathis, Mark Michael

2000-01-01T23:59:59.000Z

348

Quasiparticle lifetimes in magnesium clusters modeled by self-consistent GW? calculations  

E-Print Network [OSTI]

Quasiparticle (QP) lifetimes in magnesium clusters are calculated using many-body Green's-function theory. We analyze the effect of the self-consistency of the one-particle Green's function G on the calculations and ...

He, Yi

349

Project W-320, 241-C-106 sluicing: Civil/structural calculations. Volume 8  

SciTech Connect (OSTI)

This supporting document has been prepared to make the FDNW civil/structural calculations for Project W-320 readily retrievable.

Bailey, J.W.

1998-07-23T23:59:59.000Z

350

Interactions of biopolymers with silica surfaces: Force measurements and electronic structure calculation studies  

E-Print Network [OSTI]

calculation studies Kideok D. Kwon a,*, Virginia Vadillo-Rodriguez b , Bruce E. Logan b , James D. Kubicki a

351

A SIMPLIFIED PROCEDURE FOR CALCULATING THE EFFECTS OF DAYLIGHT FROM CLEAR SKIES  

E-Print Network [OSTI]

J. , "The Calculation of Daylight Factor for Clear Skyand Predetermination of Daylight Illumination," ILLUMINATINGA MEASURING DIAGRAM FOR DAYLIGHT ILLUMINATION, Batsford,

Bryan, Harvey J.

2012-01-01T23:59:59.000Z

352

Project W-320, 241-C-106 sluicing: Civil/structural calculations. Volume 5  

SciTech Connect (OSTI)

This supporting document has been prepared to make the FDNW calculations for Project W-320 readily retrievable.

Bailey, J.W.

1998-07-24T23:59:59.000Z

353

E-Print Network 3.0 - appendix vi calculation Sample Search Results  

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

facility, calculations showing compliance... ) (D) (vi) The noise emission abatement system; Appendix B (h) ... Source: California Energy Commission Collection: Energy...

354

The Use of Graphics Calculator in a Matriculation Statistics Classroom: A Malaysian Perspective  

E-Print Network [OSTI]

graphics calculator for five weeks showed significantly greater improvement on their mathematics achievement than students in the control

Krishnan, Saras; Idris, Noraini

2013-01-01T23:59:59.000Z

355

Project W-320, 241-C-106 sluicing electrical calculations, Volume 1  

SciTech Connect (OSTI)

This supporting document has been prepared to make the FDNW calculations for Project W-320, readily retrievable.

Bailey, J.W.

1998-08-07T23:59:59.000Z

356

Calculating Wind Integration Costs: Separating Wind Energy Value from Integration Cost Impacts  

SciTech Connect (OSTI)

Accurately calculating integration costs is important so that wind generation can be fairly compared with alternative generation technologies.

Milligan, M.; Kirby, B.

2009-07-01T23:59:59.000Z

357

New Soft-Core Potential Function for Molecular Dynamics Based Alchemical Free Energy Calculations  

E-Print Network [OSTI]

New Soft-Core Potential Function for Molecular Dynamics Based Alchemical Free Energy Calculations accurate free energy calculations based on molecular dynamics simulations. A thermodynamic integration scheme is often used to calculate changes in the free energy of a system by integrating the change

de Groot, Bert

358

Framework for Coupling Room Air Models to Heat Balance Model Load and Energy Calculations (RP-1222)  

E-Print Network [OSTI]

1 Framework for Coupling Room Air Models to Heat Balance Model Load and Energy Calculations (RP in a program for hourly load calculations of a single thermal zone. The heat balance model for load and energy to heat balance model load and energy calculations," HVAC&R Research, 10(2), 91-111. #12;2 · Mixed

Chen, Qingyan "Yan"

359

RIS-M-2185 CALCULATION OF HEAT RATING AND BURN-UP FOR TEST FUEL PINS  

E-Print Network [OSTI]

RISØ-M-2185 CALCULATION OF HEAT RATING AND BURN-UP FOR TEST FUEL PINS IRRADIATED IN DR3 C. Bagger of fuel pins irradiated in HP1 rigs. The calculations are carried out rather detailed, especially of the data. INIS Descriptors . BURN-UP, CALORIMETRY, COMPUTER CALCULATIONS, DR-3, FISSION, FUEL ASSEMBLIES

360

First-principles calculations of twin-boundary and stacking-fault energies in magnesium  

E-Print Network [OSTI]

First-principles calculations of twin-boundary and stacking-fault energies in magnesium Y. Wang and stacking faults in metal magnesium have been calculated using first-principles supercell approach. Four. Keywords: Magnesium; Interfaces; Twinning; First-principles calculation Magnesium alloys are increasingly

Chen, Long-Qing

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


361

Relativistic impulse-approximation calculation of p-bar-nucleus elastic scattering  

SciTech Connect (OSTI)

The first calculations of p-bar-nucleus elastic scattering using the relativistic impulse approximation are presented and compared with the recent 46.8-MeV p-bar-/sup 12/C elastic scattering data. The calculated cross sections agree well with the data. The differences between relativistic and nonrelativistic impulse approximation calculations using the same input are small.

Clark, B.C.; Hama, S.; McNeil, J.A.; Mercer, R.L.; Ray, L.; Serot, B.D.; Sparrow, D.A.; Stricker-Bauer, K.

1984-10-08T23:59:59.000Z

362

Neutron Noise Calculations in Hexagonal Geometry and Comparison with Analytical Solutions  

E-Print Network [OSTI]

for addressing the noise calculations of light water reactors ~LWRs! in Cartesian geometries.3 This tool instability, etc. Extension of the noise calculation method to other reactor types such as Russian VVERsNeutron Noise Calculations in Hexagonal Geometry and Comparison with Analytical Solutions Hoai Nam

Demazière, Christophe

363

12.2001 . Using of Unitarity Equations for the Calculation of Fermion Interaction  

E-Print Network [OSTI]

of calculations performed for the research reactor WWR-M at Gatchïðåïðèíòû 12.2001 ã. Using of Unitarity Equations for the Calculation of Fermion Interaction amplitudes in the superstring theory are used to calculate the interaction amplitudes including the Ramond

Titov, Anatoly

364

Calculating kinetics parameters and reactivity changes with continuous-energy Monte Carlo  

SciTech Connect (OSTI)

The iterated fission probability interpretation of the adjoint flux forms the basis for a method to perform adjoint weighting of tally scores in continuous-energy Monte Carlo k-eigenvalue calculations. Applying this approach, adjoint-weighted tallies are developed for two applications: calculating point reactor kinetics parameters and estimating changes in reactivity from perturbations. Calculations are performed in the widely-used production code, MCNP, and the results of both applications are compared with discrete ordinates calculations, experimental measurements, and other Monte Carlo calculations.

Kiedrowski, Brian C [Los Alamos National Laboratory; Brown, Forrest B [Los Alamos National Laboratory; Wilson, Paul [UNIV. WISCONSIN

2009-01-01T23:59:59.000Z

365

New equation calculates thermal conductivities of C[sub 1]-C[sub 4] gases  

SciTech Connect (OSTI)

In the design of heat exchangers, heat-transfer coefficients are commonly calculated for individual items. These calculations require knowledge of the thermal conductivities of the species involved. The calculation require knowledge of the thermal conductivities of the species involved. The calculation of the overall heat-transfer coefficient for a heat exchanger also requires thermal conductivity data for the individual species. In fact, thermal conductivity is the fundamental property involved in heat transfer. Ordinarily, thermal conductivities are either measured experimentally or estimated using complex correlations and models. Engineers must search existing literature for the values needed. Here, a compilation of thermal conductivity data for gases is presented for a wide temperature range. Using these data with the accompanying equation will enable engineers to quickly determine values at the desired temperatures. The results are provided in an easy-to-use tabular format, which is especially helpful for rapid calculations using a personal computer or hand-held calculator.

Yaws, C.L.; Lin, X.; Bu, L.; Nijhawan, S. (Lamar Univ., Beaumont, TX (United States))

1994-04-18T23:59:59.000Z

366

On the Sensitivity of ?/? Prediction to Dose Calculation Methodology in Prostate Brachytherapy  

SciTech Connect (OSTI)

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.

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

367

Neutron/gamma coupled library generation and gamma transport calculation with KARMA 1.2  

SciTech Connect (OSTI)

KAERI has developed a lattice transport calculation code KARMA and its multi-group cross section library generation system. Recently, the multi-group cross section library generation system has included a gamma cross section generation capability and KARMA also has been improved to include a gamma transport calculation module. This paper addresses the multi-group gamma cross section generation capability for the KARMA 1.2 code and the preliminary test results of the KARMA 1.2 gamma transport calculations. The gamma transport calculation with KARMA 1.2 gives the gamma flux, gamma smeared power, and gamma energy deposition distributions. The results of the KARMA gamma calculations were compared with those of HELIOS and they showed that KARMA 1.2 gives reasonable gamma transport calculation results. (authors)

Hong, S. G. [Dept. of Nuclear Engineering, Kyung Hee Univ., 446-701 Deogyeong-daero, GiHeung-gu, Yongin, Gyeonggi-do (Korea, Republic of); Kim, K. S.; Cho, J. Y.; Lee, K. H. [Korea Atomic Energy Research Inst., 305-353 Duckjin-dong, Yuseong-gu, Daejon (Korea, Republic of)

2012-07-01T23:59:59.000Z

368

RIS-M-2299 CALCULATION OF DOSE CONSEQUENCES OF A HYPOTHETICAL  

E-Print Network [OSTI]

are calculated. The reactor is a light-water reactor located at a site representing an idealized, simplified.0. The Large Accident 5 2.1. BWR-2 6 2.2. PWR-4 7 2.3. BEK.r 8 3. REACTOR SURROUNDINGS. CALCULATION MODELS to the population are calculated. The reactor is a light-water re- actor located at a site representing an idealised

369

Statistical verification of neutron-physics programs for calculations in support of nuclear safety  

SciTech Connect (OSTI)

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.

Tebin, V. V., E-mail: tebin@vver.kiae.ru [Russian Research Centre Kurchatov Institute (Russian Federation)

2012-12-15T23:59:59.000Z

370

Literature review of United States utilities computer codes for calculating actinide isotope content in irradiated fuel  

SciTech Connect (OSTI)

This paper reviews the accuracy and precision of methods used by United States electric utilities to determine the actinide isotopic and element content of irradiated fuel. After an extensive literature search, three key code suites were selected for review. Two suites of computer codes, CASMO and ARMP, are used for reactor physics calculations; the ORIGEN code is used for spent fuel calculations. They are also the most widely used codes in the nuclear industry throughout the world. Although none of these codes calculate actinide isotopics as their primary variables intended for safeguards applications, accurate calculation of actinide isotopic content is necessary to fulfill their function.

Horak, W.C.; Lu, Ming-Shih

1991-12-01T23:59:59.000Z

371

Project 1: Part 1 Project 1 will be to calculate orthogonal polynomials ...  

E-Print Network [OSTI]

Project 1 will be to calculate orthogonal polynomials. It will have several parts. Note: The scheme code in this writeup is available in the file project1.scm, ...

2014-02-14T23:59:59.000Z

372

E-Print Network 3.0 - application au calcul Sample Search Results  

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

As a result, investigations in potential applications of Au... of the different reduction kinetics of Au and Pt ions.7 In addition, theoretical calculations also suggest that Au......

373

Nonadiabatic calculations of ultraviolet absorption cross section of sulfur monoxide: Isotopic effects on the photodissociation reaction  

SciTech Connect (OSTI)

Ultraviolet absorption cross sections of the main and substituted sulfur monoxide (SO) isotopologues were calculated using R-Matrix expansion technique. Energies, transition dipole moments, and nonadiabatic coupling matrix elements were calculated at MRCI/AV6Z level. The calculated absorption cross section of {sup 32}S{sup 16}O was compared with experimental spectrum; the spectral feature and the absolute value of photoabsorption cross sections are in good agreement. Our calculation predicts a long lived photoexcited SO* species which causes large non-mass dependent isotopic effects depending on the excitation energy in the ultraviolet region.

Danielache, Sebastian O.; Tomoya, Suzuki; Nanbu, Shinkoh [Department of Materials and Life Sciences, Faculty of Science and Technology, Sophia University, Chiyoda Ku, Tokyo 102-8554 (Japan)] [Department of Materials and Life Sciences, Faculty of Science and Technology, Sophia University, Chiyoda Ku, Tokyo 102-8554 (Japan); Kondorsky, Alexey [P. N. Lebedev Physical Institute of Russian Academy of Science, Leninsky pr., 53, Moscow, 119991 (Russian Federation) [P. N. Lebedev Physical Institute of Russian Academy of Science, Leninsky pr., 53, Moscow, 119991 (Russian Federation); Moscow Institute of Physics and Technology (State University), Institutsky per., 9, Dolgoprudny Moscow region, 141700 (Russian Federation); Tokue, Ikuo [Department of Chemistry, Faculty of Science, Niigata University, Ikarashi, Niigata 950-2181 (Japan)] [Department of Chemistry, Faculty of Science, Niigata University, Ikarashi, Niigata 950-2181 (Japan)

2014-01-28T23:59:59.000Z

374

Publications 1. "Calculation of Beam Loading in Linear Traveling Wave Electron Accelerators," Review of  

E-Print Network [OSTI]

Publications 1. "Calculation of Beam Loading in Linear Traveling Wave Electron Accelerators). 26 "Stochastic and Adiabatic Behavior of Particles Accelerated by Periodic Forces," (M. A. Lieberman

Kammen, Daniel M.

375

Application Of A Spherical-Radial Heat Transfer Model To Calculate...  

Open Energy Info (EERE)

Spherical-Radial Heat Transfer Model To Calculate Geothermal Gradients From Measurements In Deep Boreholes Jump to: navigation, search OpenEI Reference LibraryAdd to library...

376

Design of an Experimental Facility for the Validation of Cooling Load Calculation Procedures.  

E-Print Network [OSTI]

??Two test cells were constructed to validate the ASHRAE cooling load calculation procedures developed under RP-875 and codified in the ASHRAE Loads Toolkit (RP987). The… (more)

Eldridge, David Stewart

2007-01-01T23:59:59.000Z

377

E-Print Network 3.0 - atomic orbitals calculation Sample Search...  

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

THE EUROPEAN Summary: Stark eects 1 Introduction Periodic-orbit theory and, variant atomic photo-absorption spectra, closed-orbit... calculated classical properties closed...

378

Cooling load calculations for radiant systems: are they the same traditional methods?  

E-Print Network [OSTI]

heat transfer is handled in traditional cooling load calculationheat gain is well recognized by cooling load calculationload calculations for radiant systems should use the ASHRAE heat

Bauman, Fred; Feng, Jingjuan Dove; Schiavon, Stefano

2013-01-01T23:59:59.000Z

379

New Calculator Helps You Buy the Energy-Saving Vehicle of Your...  

Energy Savers [EERE]

vehicles running on alternative fuels such as electricity, ethanol, natural gas, or biodiesel. With the new calculator, which was developed by DOE's National Renewable Energy...

380

Integrated Water Treatment System (IWTS) Process Flow Diagram Mass Balance Calculations for K West Basin  

SciTech Connect (OSTI)

The purpose of this calculation is to develop the rational for the material balances that are documented in the KW Basin water system Level 1 process flow diagrams.

REED, A.V.

2000-02-28T23:59:59.000Z

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


381

E-Print Network 3.0 - acute calculous gallbladder Sample Search...  

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

brain and arterial plasma data. Radiation... -absorbed doses were calculated using the MIRD Committee scheme. Results: After 11C-NOP-1A injection, peak uptake... Analysis...

382

CATALYZED COMBUSTION IN A FLAT PLATE BOUNDARY LAYER II. NUMERICAL CALCULATIONS  

E-Print Network [OSTI]

D.G. , Fourteenth Sympo- sium (International) on Combustion,The Combustion Institute, Pittsburgh, 107 (1973). Wilson,Program for Calculation of Combustion Reaction Equilibrium

Schefer, R.

2010-01-01T23:59:59.000Z

383

Vehicle Technologies Office Merit Review 2014: First Principles Calculations and NMR Spectroscopy of Electrode Materials  

Broader source: Energy.gov [DOE]

Presentation given by [company name] at 2014 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Office Annual Merit Review and Peer Evaluation Meeting about first principles calculations...

384

E-Print Network 3.0 - accident response calculations Sample Search...  

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

effect of such variables needs to be calculated... in many countries. The majority of bicycle-motor vehicle (BMV) accidents occur at intersections. In order... to reduce the...

385

Quantum mechanical method of fragment's angular and energy distribution calculation for binary and ternary fission  

SciTech Connect (OSTI)

In the framework of quantum-mechanical fission theory, the method of calculation for partial fission width amplitudes and asymptotic behavior of the fissile nucleus wave function with strong channel coupling taken into account has been suggested. The method allows one to solve the calculation problem of angular and energy distribution countation for binary and ternary fission.

Kadmensky, S. G., E-mail: kadmensky@phys.vsu.ru; Titova, L. V.; Pen'kov, N. V. [Voronezh State University (Russian Federation)

2006-08-15T23:59:59.000Z

386

Static Variable Ordering in ZBDDs for Path Delay Fault Coverage Calculation  

E-Print Network [OSTI]

to calculate exact PDF coverage nonenumeratively. Each PDF is modeled as a subset of all nets in a circuitStatic Variable Ordering in ZBDDs for Path Delay Fault Coverage Calculation Fatih Kocan, Mehmet Gunes, Mitchell A. Thornton Southern Methodist University, Dallas, Texas, U.S.A. Abstract Zero

Gunes, Mehmet Hadi

387

Per Capita Consumption The NMFS calculation of per capita consumption is  

E-Print Network [OSTI]

Per Capita Consumption 73 The NMFS calculation of per capita consumption is based to estimate per capita consumption. Data for the model are derived primarily from second- ary sources a significant effect on the resulting calculation. U.S. per capita consumption of fish and shellfish was 15

388

Per Capita Consumption The NMFS calculation of per capita consumption is  

E-Print Network [OSTI]

Per Capita Consumption 73 The NMFS calculation of per capita consumption is based to estimate per capita consumption. Data for the model are derived primarily from second- ary sources effect on the resulting calculation. U.S. per capita consumption of fish and shellfish was 16.0 pounds

389

Per Capita Consumption The NMFS calculation of per capita consumption is  

E-Print Network [OSTI]

Per Capita Consumption 73 The NMFS calculation of per capita consumption is based to estimate per capita consumption. Data for the model are derived primarily from second- ary sources effect on the resulting calculation. U.S. per capita consumption of fish and shellfish was 16.5 pounds

390

Per Capita Consumption The NMFS calculation of per capita consumption is  

E-Print Network [OSTI]

Per Capita Consumption 73 The NMFS calculation of per capita consumption is based to estimate per capita consumption. Data for the model are derived primarily from second- ary sources effect on the resulting calculation. U.S. per capita consumption of fish and shellfish was 16.3 pounds

391

Per Capita Consumption The NMFS calculation of per capita consumption is  

E-Print Network [OSTI]

Per Capita Consumption 84 The NMFS calculation of per capita consumption is based to estimate per capita consumption. Data for the model are derived primarily from second- ary sources effect on the resulting calculation. U.S. per capita consumption of fish and shellfish was 16.3 pounds

392

A Comparison of the AC and DC Power Flow Models for LMP Calculations  

E-Print Network [OSTI]

A Comparison of the AC and DC Power Flow Models for LMP Calculations Thomas J. Overbye, Xu Cheng power flow model for LMP-based market calculations. The paper first provides a general discussion of balanced, three phase, electric power transmission networks is through the solution of the power flow. From

393

A method for calculating wide band electromagnetic interference from power line corona  

SciTech Connect (OSTI)

An algorithm for calculating electromagnetic interference from power line corona for a range of frequencies from 100 kHz to 30 MHz is demonstrated. It can be used for calculations at any distance or direction from the line. The algorithm incorporates an existing generation function which has been optimized by comparison to long term electromagnetic interference measurements.

Olsen, R.G. [Washington State Univ., Pullman, WA (United States). School of Electrical Engineering and Computer Science] [Washington State Univ., Pullman, WA (United States). School of Electrical Engineering and Computer Science; Schennum, S.D. [Gonzaga Univ., Spokane, WA (United States)] [Gonzaga Univ., Spokane, WA (United States)

1995-07-01T23:59:59.000Z

394

Detecting Protein-Protein Interaction Decoys using Fast Free Energy Calculations  

E-Print Network [OSTI]

Detecting Protein-Protein Interaction Decoys using Fast Free Energy Calculations Christopher James, Generalized Belief Propagation, Free Energy, Protein- Protein Interactions #12;Abstract We present a physics for a given complex, and Generalized Belief Propa- gation to perform the free energy calculation. Our method

Langmead, Christopher James

395

Studies on free energy calculations. I. Thermodynamic integration using a polynomial path  

E-Print Network [OSTI]

Studies on free energy calculations. I. Thermodynamic integration using a polynomial path Haluk in the free energy of hydration between the C, and aR conformations of alanine dipeptide at infinite dilution equilibria is determined by free energy ditferences, the calculation of the free energies has long been

Mezei, Mihaly

396

STEADY STATE FLAMMABLE GAS RELEASE RATE CALCULATION AND LOWER FLAMMABILITY LEVEL EVALUATION FOR HANFORD TANK WASTE  

SciTech Connect (OSTI)

Assess the steady-state flammability level at normal and off-normal ventilation conditions. The hydrogen generation rate was calculated for 177 tanks using the rate equation model. Flammability calculations based on hydrogen, ammonia, and methane were performed for 177 tanks for various scenarios.

HU TA

2009-10-26T23:59:59.000Z

397

Improved quantum Monte Carlo calculation of the ground-state energy of the hydrogen molecule  

E-Print Network [OSTI]

variational energies. The accuracy of the new Monte Carlo energy is approximately equal to that of recentImproved quantum Monte Carlo calculation of the ground-state energy of the hydrogen molecule Bin Carlo calculation of the nonrelativistic ground-state energy of the hydrogen molecule, without the use

Anderson, James B.

398

Beam dynamics in accelerators for medical applications: from calculations to machine performance  

E-Print Network [OSTI]

Beam dynamics in accelerators for medical applications: from calculations to machine performance S, z', W, RF-phase) at each time-moment for each particle in the accelerating bunch use cylindrical, Novosibirsk, Russian Federation #12;Main results of calculations 6 ...transverse beam size during acceleration

399

Efficiency of pump absorption in double-clad fiber amplifiers. III. Calculation of modes  

E-Print Network [OSTI]

Efficiency of pump absorption in double-clad fiber amplifiers. III. Calculation of modes Dmitrii us to calculate the efficiency of an incoherent pump in general-geometry double-clad fibers. This approach yields accurate estimates of the absorption rate of each mode of the pump in the first order

Kouznetsov, Dmitrii

400

Electronic structure calculations of radical reactions for poly(methyl methacrylate) degradation  

E-Print Network [OSTI]

exposed to UV light in low-Earth orbit (LEO) conditions experience degradation. Under LEO conditionsElectronic structure calculations of radical reactions for poly(methyl methacrylate) degradation to calculate the reaction energetics for decomposition reactions of radicals formed from UV radiation

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


401

Understanding the NMR shifts in paramagnetic transition metal oxides using density functional theory calculations  

E-Print Network [OSTI]

obvious. In this paper, we show by means of density functional theory DFT calcula- tions that a rationalUnderstanding the NMR shifts in paramagnetic transition metal oxides using density functional functional theory DFT calculations in the generalized gradient approximation. For each compound, we calculate

Ceder, Gerbrand

402

Accurate Thermodynamic Model for the Calculation of H2S Solubility in Pure Water and Brines  

E-Print Network [OSTI]

Accurate Thermodynamic Model for the Calculation of H2S Solubility in Pure Water and Brines Zhenhao, 2007 A thermodynamic model calculating the solubility of hydrogen sulfide (H2S) in pure water phase. With this specific interaction approach, this model is able to predict H2S solubility in other

Zhu, Chen

403

Enthalpies of formation of magnesium compounds from first-principles calculations  

E-Print Network [OSTI]

Enthalpies of formation of magnesium compounds from first-principles calculations Hui Zhang t An energetics database of binary magnesium compounds has been developed from first-principles calculations. Introduction Magnesium alloys are of great importance to the industrial world. With a density of 1.741 g/cm3

Chen, Long-Qing

404

A Critical Assessment of Computer Tools for Calculating Composite Wind Turbine Blade Properties  

E-Print Network [OSTI]

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

Yu, Wenbin

405

Variational Calculation on the Helium Atom Using a Hydrogenic Trial Wave Function Frank Rioux  

E-Print Network [OSTI]

kinetic energy: 2 0 r r ,( ) 1 2 r - 2 r r r ,( )( )d d 2 4 r 2 d assume 0>, simplify 2 Calculate electronnucleus potential energy: 2 0 r r ,( ) 2- r r ,( ) 4 r 2 d assume 0>, simplify 4 r e 2-( ) r e 2-( ) r 1-+ - r b. Calculate the electronelectron potential energy using result

Rioux, Frank

406

Variational Calculation on the Helium Atom Using a Trigonometric Trial Wave Function Frank Rioux  

E-Print Network [OSTI]

kinetic energy: 2 0 r r ,( ) 1 2 r - 2 r r r ,( )( )d d 2 4 r 2 d assume 0>, simplify 1 3 2 12 2 + 2 Calculate electronnucleus potential energy: 2 0 r r ,( ) 2- r r ,( ) 4 r 2 d assume 0>, simplify 48-( ) ln 2( ) 2 Calculate electronelectron potential energy: 0 r r ,( )2

Rioux, Frank

407

A transport based one-dimensional perturbation code for reactivity calculations in metal systems  

SciTech Connect (OSTI)

A one-dimensional reactivity calculation code is developed using first order perturbation theory. The reactivity equation is based on the multi-group transport equation using the discrete ordinates method for angular dependence. In addition to the first order perturbation approximations, the reactivity code uses only the isotropic scattering data, but cross section libraries with higher order scattering data can still be used with this code. The reactivity code obtains all the flux, cross section, and geometry data from the standard interface files created by ONEDANT, a discrete ordinates transport code. Comparisons between calculated and experimental reactivities were done with the central reactivity worth data for Lady Godiva, a bare uranium metal assembly. Good agreement is found for isotopes that do not violate the assumptions in the first order approximation. In general for cases where there are large discrepancies, the discretized cross section data is not accurately representing certain resonance regions that coincide with dominant flux groups in the Godiva assembly. Comparing reactivities calculated with first order perturbation theory and a straight {Delta}k/k calculation shows agreement within 10% indicating the perturbation of the calculated fluxes is small enough for first order perturbation theory to be applicable in the modeled system. Computation time comparisons between reactivities calculated with first order perturbation theory and straight {Delta}k/k calculations indicate considerable time can be saved performing a calculation with a perturbation code particularly as the complexity of the modeled problems increase.

Wenz, T.R.

1995-02-01T23:59:59.000Z

408

Calculation of higher moments of the neutron multiplication process in a time-varying medium  

E-Print Network [OSTI]

, which only calculates this new component added and com- pletely ignores the zero-power reactor noiseCalculation of higher moments of the neutron multiplication process in a time-varying medium Y Available online 20 April 2007 Abstract The zero-power reactor noise theory in a steady neutron multiplying

Pázsit, Imre

409

Evaluation of a new commercial Monte Carlo dose calculation algorithm for electron beams  

SciTech Connect (OSTI)

Purpose: In this report the authors present the validation of a Monte Carlo dose calculation algorithm (XiO EMC from Elekta Software) for electron beams. Methods: Calculated and measured dose distributions were compared for homogeneous water phantoms and for a 3D heterogeneous phantom meant to approximate the geometry of a trachea and spine. Comparisons of measurements and calculated data were performed using 2D and 3D gamma index dose comparison metrics. Results: Measured outputs agree with calculated values within estimated uncertainties for standard and extended SSDs for open applicators, and for cutouts, with the exception of the 17 MeV electron beam at extended SSD for cutout sizes smaller than 5 × 5 cm{sup 2}. Good agreement was obtained between calculated and experimental depth dose curves and dose profiles (minimum number of measurements that pass a 2%/2 mm agreement 2D gamma index criteria for any applicator or energy was 97%). Dose calculations in a heterogeneous phantom agree with radiochromic film measurements (>98% of pixels pass a 3 dimensional 3%/2 mm ?-criteria) provided that the steep dose gradient in the depth direction is considered. Conclusions: Clinically acceptable agreement (at the 2%/2 mm level) between the measurements and calculated data for measurements in water are obtained for this dose calculation algorithm. Radiochromic film is a useful tool to evaluate the accuracy of electron MC treatment planning systems in heterogeneous media.

Vandervoort, Eric J., E-mail: evandervoort@toh.on.ca; Cygler, Joanna E. [Department of Medical Physics, The Ottawa Hospital Cancer Centre, The University of Ottawa, Ottawa, Ontario K1H 8L6 (Canada) [Department of Medical Physics, The Ottawa Hospital Cancer Centre, The University of Ottawa, Ottawa, Ontario K1H 8L6 (Canada); The Faculty of Medicine, The University of Ottawa, Ottawa, Ontario K1H 8M5 (Canada); Department of Physics, Carleton University, Ottawa, Ontario K1S 5B6 (Canada); Tchistiakova, Ekaterina [Department of Medical Physics, The Ottawa Hospital Cancer Centre, The University of Ottawa, Ottawa, Ontario K1H 8L6 (Canada) [Department of Medical Physics, The Ottawa Hospital Cancer Centre, The University of Ottawa, Ottawa, Ontario K1H 8L6 (Canada); Department of Medical Biophysics, University of Toronto, Ontario M5G 2M9 (Canada); Heart and Stroke Foundation Centre for Stroke Recovery, Sunnybrook Research Institute, University of Toronto, Ontario M4N 3M5 (Canada); La Russa, Daniel J. [Department of Medical Physics, The Ottawa Hospital Cancer Centre, The University of Ottawa, Ottawa, Ontario K1H 8L6 (Canada) and The Faculty of Medicine, The University of Ottawa, Ottawa, Ontario K1H 8M5 (Canada)] [Department of Medical Physics, The Ottawa Hospital Cancer Centre, The University of Ottawa, Ottawa, Ontario K1H 8L6 (Canada) and The Faculty of Medicine, The University of Ottawa, Ottawa, Ontario K1H 8M5 (Canada)

2014-02-15T23:59:59.000Z

410

On how to calculate methane lifetime from OH concentrations (FORTRAN): Integer I, J, L ! counters  

E-Print Network [OSTI]

On how to calculate methane lifetime from OH concentrations (FORTRAN): Integer I, J, L ! counters_ch4 ! methane lifetime (years) C Initialize: ch4_sum=0. yield=0. C Calculate sums: Do J = 1 , JM Do I in tropospheric ozone and methane; global 3D model studies, Atmospheric Environment, 33, 961-977, 1999

Haak, Hein

411

Computer Graphics in Real-time Docking with Energy Calculation and Minimization  

E-Print Network [OSTI]

Computer Graphics in Real-time Docking with Energy Calculation and Minimization N. Pattabiraman, M. Levitt*, T.E. Ferrin, R. Langridge Computer Graphics Laboratory, Department of Pharmaceutical Chemistry 1985 We describe a real-time docking method using molecular graphics and high-speed calculation

Levitt, Michael

412

CALCULATION AND USE OF STEAM/WATER RELATIVE PERMEABILITIES IN GEOTHERMAL RESERVOIRS  

E-Print Network [OSTI]

c c c i i c I CALCULATION AND USE OF STEAM/WATER RELATIVE PERMEABILITIES IN GEOTHERMAL RESERVOIRS to calculate the steam/water relative permeabilities in geothermal reservoirs was developed and applied curves as a basis for analysis of future well tests for geothermal reservoirs. c ii #12;TABLE OF CONTENTS

Stanford University

413

UDC 622.276 A NEW APPROACH CALCULATE OIL-GAS RATIO  

E-Print Network [OSTI]

UDC 622.276 A NEW APPROACH CALCULATE OIL-GAS RATIO FOR GAS CONDENSATE AND VOLATILE OIL RESERVOIRS. In this work, we develop a new approach to calculate oil-gas ratio (Rv) by matching PVT experimental data laboratory analysis of eight gas condensate and five volatile oil fluid samples; selected under a wide range

Fernandez, Thomas

414

Three-dimensional calculation of field emission from carbon nanotubes using a transfer-matrix methodology  

E-Print Network [OSTI]

Three-dimensional calculation of field emission from carbon nanotubes using a transfer- matrix simulations of field emission from carbon nanotubes, using a transfer-matrix methodology. By repeating field, as shown by recent ab-initio calculations [10]. To study field emission from carbon nanotubes, we

Mayer, Alexandre

415

Exchange-only optimized effective potential calculation of excited state spectra for He and Be atoms.  

SciTech Connect (OSTI)

The optimized effective potential (OEP) method allows orbital-dependent functionals to be used in density functional theory (DFT), which, in particular, allows exact exchange formulations of the exchange energy to be used in DFT calculations. Because the exact exchange is inherently self-interaction correcting, the resulting OEP calculations have been found to yield superior band-gaps for condensed-phase systems. Here we apply these methods to the isolated atoms He and Be, and compare to high quality experiments and calculations to demonstrate that the orbital energies accurately reproduce the excited state spectrum for these species. These results suggest that coupling the exchange-only OEP calculations with proper (orbital-dependent or other) correlation functions might allow quantitative accuracy from DFT calculations.

Desjarlais, Michael Paul; Muller, Richard Partain

2006-02-01T23:59:59.000Z

416

First principles calculation of polarization induced interfacial charges in GaN/AlN heterostructures  

E-Print Network [OSTI]

We propose a new method to calculate polarization induced interfacial charges in semiconductor heterostructures using classical electrostatics applied to real-space band diagrams from first principles calculations and apply it to GaN/AlN heterostructures with ultrathin AlN layers (4-6 monolayers). We show that the calculated electric fields and interfacial charges are independent of the exchange-correlation functionals used (local-density approximation and hybrid functionals). We also find the calculated interfacial charge of (6.8 +/- 0.4) x 10^13 cm-2 to be in excellent agreement with experiments and the value of 6.58 x 10^13 cm-2 calculated from bulk polarization constants, validating the use of bulk constants even for very thin films.

Rohan Mishra; Oscar D. Restrepo; Siddharth Rajan; Wolfgang Windl

2011-05-17T23:59:59.000Z

417

Guideline of Monte Carlo calculation. Neutron/gamma ray transport simulation by Monte Carlo method  

E-Print Network [OSTI]

This report condenses basic theories and advanced applications of neutron/gamma ray transport calculations in many fields of nuclear energy research. Chapters 1 through 5 treat historical progress of Monte Carlo methods, general issues of variance reduction technique, cross section libraries used in continuous energy Monte Carlo codes. In chapter 6, the following issues are discussed: fusion benchmark experiments, design of ITER, experiment analyses of fast critical assembly, core analyses of JMTR, simulation of pulsed neutron experiment, core analyses of HTTR, duct streaming calculations, bulk shielding calculations, neutron/gamma ray transport calculations of the Hiroshima atomic bomb. Chapters 8 and 9 treat function enhancements of MCNP and MVP codes, and a parallel processing of Monte Carlo calculation, respectively. An important references are attached at the end of this report.

2002-01-01T23:59:59.000Z

418

Bounding Radionuclide Inventory and Accident Consequence Calculation for the 1L Target  

SciTech Connect (OSTI)

A bounding radionuclide inventory for the tungsten of the Los Alamos Neutron Science Center (LANSCE) IL Target is calculated. Based on the bounding inventory, the dose resulting from the maximum credible incident (MCI) is calculated for the maximally exposed offsite individual (MEOl). The design basis accident involves tungsten target oxidation following a loss of cooling accident. Also calculated for the bounding radionuclide inventory is the ratio to the LANSCE inventory threshold for purposes of inventory control as described in the target inventory control policy. A bounding radionuclide inventory calculation for the lL Target was completed using the MCNPX and CINDER'90 codes. Continuous beam delivery at 200 {micro}A to 2500 mA{center_dot}h was assumed. The total calculated activity following this irradiation period is 205,000 Ci. The dose to the MEOI from the MCI is 213 mrem for the bounding inventory. The LANSCE inventory control threshold ratio is 132.

Kelsey, Charles T. IV [Los Alamos National Laboratory

2011-01-01T23:59:59.000Z

419

DFT calculations of EPR parameters of transition metal complexes: Implications for catalysis  

SciTech Connect (OSTI)

Transition metal and ligand hyperfine coupling constants for paramagnetic vanadium and copper model complexes have been calculated using DFT methods that are available in commercial software packages. Variations in EPR parameters with ligand identity and ligand orientation are two of the trends that have been investigated with DFT calculations. For example, the systematic variation of the vanadium hyperfine coupling constant with orientation for an imidazole ligand in a VO2+ complex has been observed experimentally and has also been reproduced by DFT calculations. Similarly, changes in the vanadium hyperfine coupling constant with ligand binding have been calculated using model complexes and DFT methods. DFT methods were also used to calculate ligand hyperfine coupling constants in transition metal systems. The variation of the proton hyperfine coupling constant with water ligand orientation was investigated for [VO(H2O)5]2+ and the results were used to interpret high resolution EPR data of VO2+-exchanged zeolites. Nitrogen hyperfine and quadrupole coupling constants for VO2+ model complexes were calculated and compared with experimental data. The computational results were used to enhance the interpretation of the EPR data for vanadium-exchanged zeolites which are promising catalytic materials. The implications of the DFT calculations of EPR parameters with respect to catalysis will be discussed

Saladino, Alexander C.; Larsen, Sarah C.

2005-07-15T23:59:59.000Z

420

Theoretical calculation of medium-energy proton-induced reactions on Al, Zr, and Pb  

SciTech Connect (OSTI)

The intranuclear cascade model of nuclear reactions was used to calculate double differential cross sections for the (p,xn) reaction. The calculations were performed with a generalized version of the code VEGAS, CLUST. Model predictions are compared with recent experimental data. Calculated fast-particle spectral shapes at low angles are reproduced reasonably well for the experimental data. As one possible improvement to the model, the proton reaction cross sections were estimated independently using the prescriptions of Karol, and DeVries and Peng. The systematic trends that emerge from this analysis are discussed. 12 refs., 5 figs.

Ramavataram, S.; Divadeenam, M.; Ward, T.E.

1988-01-01T23:59:59.000Z

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


421

Calculation of the Naval Long and Short Waste Package Three-Dimensional Thermal Interface Temperatures  

SciTech Connect (OSTI)

The purpose of this calculation is to evaluate the thermal performance of the Naval Long and Naval Short spent nuclear fuel (SNF) waste packages (WP) in the repository emplacement drift. The scope of this calculation is limited to the determination of the temperature profiles upon the surfaces of the Naval Long and Short SNF waste package for up to 10,000 years of emplacement. The temperatures on the top of the outside surface of the naval canister are the thermal interfaces for the Naval Nuclear Propulsion Program (NNPP). The results of this calculation are intended to support Licensing Application design activities.

H. Marr

2006-10-25T23:59:59.000Z

422

Improved calculations of the lowest vibrational transitions in HeH{sup +}  

SciTech Connect (OSTI)

More accurate variational calculations of the lowest three pure vibrational states (v=0,1,2) of the {sup 4}HeH{sup +} molecular ion have been carried out without assuming the Born-Oppenheimer approximation. In the calculations we included the complete set of {alpha}{sup 2} relativistic corrections, i.e., mass-velocity, Darwin, spin-spin, and orbit-orbit. This allowed us to improve the agreement between the theory and the experiment for the vibrational frequencies of the 1{yields}0 and 2{yields}1 transitions as compared to our previous calculations [Stanke et al., Phys. Rev. Lett. 96, 233002 (2006)].

Bubin, Sergiy [Department of Chemistry, University of Arizona, Tucson, Arizona 85721 (United States); Stanke, Monika [Department of Chemistry, University of Arizona, Tucson, Arizona 85721 (United States); Institute of Physics, Nicholas Copernicus University, ulica Grudziadzka 5, PL 87-100 Torun (Poland); Kedziera, Dariusz [Department of Chemistry, Nicholas Copernicus University, ulica Gagarina 7, PL 87-100 Torun (Poland); Adamowicz, Ludwik [Department of Chemistry, University of Arizona, Tucson, Arizona 85721 (United States); Department of Physics, University of Arizona, Tucson, Arizona 85721 (United States)

2007-08-15T23:59:59.000Z

423

Calculation of delayed-neutron energy spectra in a QRPA-Hauser-Feshbach model  

SciTech Connect (OSTI)

Theoretical {beta}-delayed-neutron spectra are calculated based on the Quasiparticle Random-Phase Approximation (QRPA) and the Hauser-Feshbach statistical model. Neutron emissions from an excited daughter nucleus after {beta} decay to the granddaughter residual are more accurately calculated than in previous evaluations, including all the microscopic nuclear structure information, such as a Gamow-Teller strength distribution and discrete states in the granddaughter. The calculated delayed-neutron spectra agree reasonably well with those evaluations in the ENDF decay library, which are based on experimental data. The model was adopted to generate the delayed-neutron spectra for all 271 precursors.

Kawano, Toshihiko [Los Alamos National Laboratory; Moller, Peter [Los Alamos National Laboratory; Wilson, William B [Los Alamos National Laboratory

2008-01-01T23:59:59.000Z

424

Algorithm for calculation of characterisitcs of thermionic electricity-generating assemblies  

SciTech Connect (OSTI)

A numerical algorithm has been developed for calculating the kinetic characteristics of electricity-generating coaxial cells and assemblies; it is based on separate solution of the equations describing the thermal and electrical processes with their subsequent coordination by way of the volt-ampere characteristics of an elementary thermionic converter by means of piecewise-linear approximation of the nonlinear characteristics at the operating points. The possibilities and advantages of the proposed calculation algorithm for investigation of the transients occurring in the course of operation of the electricity generating assemblies (EGA) are indicated. Results are reported for sample calculations of several EGA static and kinetic characteristics. 10 refs.

Babushkin, Yu.V.; Mendel'baum, M.A.; Savinov, A.P.; Sinyavskii, V.V.

1981-01-01T23:59:59.000Z

425

A programme for electron-impact broadening parameter calculations of ionized rare-earth element lines  

E-Print Network [OSTI]

In order to provide atomic data needed for astrophysical investigations, a set of electron-impact broadening parameters for ionized rare-earth element lines should be calculated. We are going to calculate the electron-impact broadening parameters for more than 50 transitions of ionized rare-earth elements. Taking into account that the spectra of these elements are very complex, for calculation we can use the modified semiempirical approach - MSE or simplified MSE. Also, we can estimate these parameters on the basis of regularities and systematic trends.

L. C. Popovic; M. S. Dimitrijevic

1998-05-15T23:59:59.000Z

426

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

E-Print Network [OSTI]

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

S. M. Bilenky; J. A. Grifols

2002-11-07T23:59:59.000Z

427

Calculation of large ion densities under HVdc transmission lines by the finite difference method  

SciTech Connect (OSTI)

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.

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

428

Use of computers for making multicomponent distillation calculations for reboiler-absorbers  

E-Print Network [OSTI]

/vli are those which are in material balance and in agreement with the specifications. The relationship may be stated as follows. (20) In a similar manner, the quantity 01 is used to express the relationship between the calculated and corrected values of wli... calculation and the minimum rate to I/1. 2 times the value used to make the calculation. At the end of the twentieth trial, p was further reduced to 0. 025 and at the end of the thirtieth trial, p was reduced to 0. 01. For other problems presented herein...

Canik, Leebert J

1961-01-01T23:59:59.000Z

429

Calculational procedure for multicomponent distillation columns with side-stream-strippers  

E-Print Network [OSTI]

, Based u ion tne Ji composition calculated by direct-iter;ition, the coi i icte. . te. . i, erature , irofilo ives ca' culated using iiewton's nethod. The above c. . lcul itio ial procedure w. - found to diver "e if the calcul. i ed i iate c&m csitions...M point calculations based on these oalculatcd cccqxositions, iXthsr Hex&ton&s mthod ca' ths . uxthcxx of interpolation ~ ~) ~ as dsscnibed by Sorolnikof' (27)& may be employed, Thc difference either in the m3culctod tempera5xres frcm trial to trix...

Dickey, Billy Ray

1962-01-01T23:59:59.000Z

430

Calculation of volumetric behavior of hydrocarbon fluids when subjected to laboratory liberation processes  

E-Print Network [OSTI]

. The convergence pressure used, to select the constants bi~ is calculated in Subroutine Convp. An example of the ai equation (18) is as follows: For i = 0 2 / a0 b00 + b01 (~J b02 (~g + b0y (~J 04 10 05 TV 06 ~ (19) etc ~ through i = 3 ~ It can be seen from... calculated P/PKC for given tolerance~ ((WASP(RATPG-RATPA)) ? . 01) ~ 11 ' If. tolerance is exceeded set PKA = PKG and return to step 2. 12 ~ If correct convergence pressure is not calculated in 20 iterations return to main program. 15. If tolerance (see...

Scott, Stephen Gary

1964-01-01T23:59:59.000Z

431

Sensitivity and uncertainty analyses for thermo-hydraulic calculation of research reactor  

SciTech Connect (OSTI)

The sensitivity and uncertainty analysis of input parameters on thermohydraulic calculations for a research reactor has successfully done in this research. The uncertainty analysis was carried out on input parameters for thermohydraulic calculation of sub-channel analysis using Code COOLOD-N. The input parameters include radial peaking factor, the increase bulk coolant temperature, heat flux factor and the increase temperature cladding and fuel meat at research reactor utilizing plate fuel element. The input uncertainty of 1% - 4% were used in nominal power calculation. The bubble detachment parameters were computed for S ratio (the safety margin against the onset of flow instability ratio) which were used to determine safety level in line with the design of 'Reactor Serba Guna-G. A. Siwabessy' (RSG-GA Siwabessy). It was concluded from the calculation results that using the uncertainty input more than 3% was beyond the safety margin of reactor operation.

Hartini, Entin; Andiwijayakusuma, Dinan [Center for Development of Nuclear Informatics - National Nuclear Energy Agency PUSPIPTEK, Serpong, Tangerang, Banten (Indonesia)] [Center for Development of Nuclear Informatics - National Nuclear Energy Agency PUSPIPTEK, Serpong, Tangerang, Banten (Indonesia); Isnaeni, Muh Darwis [Center for Reactor Technology and Nuclear Safety- National Nuclear Energy Agency PUSPIPTEK, Serpong, Tangerang, Banten (Indonesia)] [Center for Reactor Technology and Nuclear Safety- National Nuclear Energy Agency PUSPIPTEK, Serpong, Tangerang, Banten (Indonesia)

2013-09-09T23:59:59.000Z

432

Comment on ``Success of collinear expansion in the calculation of induced gluon emission''  

E-Print Network [OSTI]

We show that the arguments against our recent paper on the failure of the collinear expansion in the calculation of the induced gluon emission raised by X.N. Wang are either incorrect or irrelevant.

P. Aurenche; B. G. Zakharov; H. Zaraket

2008-06-01T23:59:59.000Z

433

Calculations of thermal-reactor spent-fuel nuclide inventories and comparisons with measurements  

SciTech Connect (OSTI)

Comparisons with integral measurements have demonstrated the accuracy of CINDER codes and libraries in calculating aggregate fission-product properties, including neutron absorption, decay power, and decay spectra. CINDER calculations have, alternatively, been used to supplement measured integral data describing fission-product decay power and decay spectra. Because of the incorporation of the extensive actinide library and the use of ENDF/B-V data, it is desirable to compare the inventory of individual nuclides obtained from tandem EPRI-CELL/CINDER-2 calculations with those determined in documented benchmark inventory measurements of spent reactor fuel. The development of the popular /sup 148/Nd burnup measurement procedure is outlined, and areas of uncertainty in it and lack of clarity in its interpretation are indicated. Six inventory samples of varying quality and completeness are examined. The power histories used in the calculations have been listed for other users.

Wilson, W.B.; LaBauve, R.J.; England, T.R.

1982-01-01T23:59:59.000Z

434

/sup 18/O as a core plus two valence neutrons: A three-body Faddeev calculation  

SciTech Connect (OSTI)

The nucleus /sup 18/O is studied assuming a three-body model: two neutrons outside an inert core of /sup 16/O: and solving the Faddeev equations. The calculated spectrum is in good agreement with experiment.

Ueta, K.; Miyake, H.; Mizukami, A.

1983-01-01T23:59:59.000Z

435

Permits and Variances for Solar Panels, Calculation of Impervious Cover (Maryland)  

Broader source: Energy.gov [DOE]

In May 2012 Maryland enacted legislation stating that any calculation of "impervious surface" required by state or local authorities as part of a permit or variance relating to zoning, construction...

436

Webinar: Using the RTU Comparison Calculator to Justify High-Efficiency Units  

Broader source: Energy.gov [DOE]

The Advanced Rooftop Unit (RTU) Campaign is working with the Pacific Northwest National Laboratory (PNNL) to update its RTU Comparison Calculator (RTUCC). Join this webinar to learn how contractors...

437

A coupled neutronics/thermalhydraulics tool for calculating fluctuations in Pressurized Water Reactors  

E-Print Network [OSTI]

Water Reactors or Heavy Water Reactors (LarssoA coupled neutronics/thermal­hydraulics tool for calculating fluctuations in Pressurized Water in neutron flux, fuel temperature, moderator den- sity and flow velocity in Pressurized Water Reactors

Demazière, Christophe

438

Hydraulic Calculations Relating to the Flooding and Draining of the Roman Colosseum for Naumachiae   

E-Print Network [OSTI]

This report includes full details of the calculations used in determining flows into and out of the Colosseum. It should be read in conjunction with the published paper in the Proceedings of ICE Civil Engineering 160 ...

Crapper, Martin

439

Calculation notes that support accident scenario and consequence of the evaporator dump  

SciTech Connect (OSTI)

The purpose of this calculation note is to provide the basis for evaporator dump consequence for the Tank Farm Safety Analysis Report (FSAR). Evaporator Dump scenario is developed and details and description of the analysis methods are provided.

Crowe, R.D., Westinghouse Hanford

1996-09-09T23:59:59.000Z

440

Calculation notes that support accident scenario and consequence of the evaporator dump  

SciTech Connect (OSTI)

The purpose of this calculation note is to provide the basis for evaporator dump consequence for the Tank Farm Safety Analysis Report (FSAR). Evaporator Dump scenario is developed and details and description of the analysis methods are provided.

Crowe, R.D.

1996-09-27T23:59:59.000Z

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


441

The work-Hamiltonian connection and the usefulness of the Jarzynski equality for free energy calculations  

E-Print Network [OSTI]

The connection between work and changes in the Hamiltonian for a system with a time-dependent Hamiltonian has recently been called into question, casting doubt on the usefulness of the Jarzynski equality for calculating ...

Zimanyi, Eric N.

442

Experimental Validation of Pore-Level Calculations of Static and Dynamic Petrophysical Properties of Clastic Rocks  

E-Print Network [OSTI]

. The calculations are based on high-resolution three-dimensional (3D) digital images of actual clastic rocks of Petroleum Engineers is prohibited. Permission to reproduce in print is restricted to an ab- stract

Torres-Verdín, Carlos

443

Density of Configurational States from First-Principles Calculations: The Phase Diagram of  

E-Print Network [OSTI]

(LGH) using interatomic interaction energies derived from density functional theory (DFT) calculations,[3­7] together with Monte Carlo (MC) simulations (called "ab initio LGH+ MC"). Once the LGH has been

444

Calculating differential cross sections for electron-impact ionization without explicit use of the asymptotic form  

SciTech Connect (OSTI)

We describe the calculation of singly differential (energy-sharing) cross sections for electron-impact ionization. First, using exterior complex scaling, we calculate the outgoing portion of the scattering wave function without explicit use of asymptotic boundary conditions. Once that wave function is known for a finite region of space, the outgoing flux can be calculated and extrapolated to large distances according to behavior that is specific to the ionization problem. The differential cross section is proportional to the outgoing flux in specific directions of a hyperspherical angle in the coordinates. Calculations on the singlet s-wave radial limit (Temkin-Poet and collinear) models of electron-hydrogen atom ionization are presented. {copyright} {ital 1997} {ital The American Physical Society}

McCurdy, C.W. [Computing Sciences, Lawrence Berkeley National Laboratory, Berkeley, California 94720 (United States)] [Computing Sciences, Lawrence Berkeley National Laboratory, Berkeley, California 94720 (United States); Rescigno, T.N. [Physics and Space Technology Directorate, Lawrence Livermore National Laboratory, Livermore, California 94550 (United States)] [Physics and Space Technology Directorate, Lawrence Livermore National Laboratory, Livermore, California 94550 (United States)

1997-12-01T23:59:59.000Z

445

Evolutionary Ecology, 1996, 10, 221-232 Calculating the ESS level  

E-Print Network [OSTI]

Evolutionary Ecology, 1996, 10, 221-232 Calculating the ESS level aggressive communication demonstrate that while a non-communicating ESS does exist, so do several others which use information

Hurd, Peter L.

446

Reminder: You may not use the calculator in your cell phone during ...  

E-Print Network [OSTI]

Reminder: You may not use the calculator in your cell phone during the exam. Note: This is NOT a practice exam. It is a collection of problems to help you review ...

447

Calculation of neutrinoless double decay matrix elements in the Interacting Boson Model  

SciTech Connect (OSTI)

We show the formalism required to calculate in the Interacting Boson Model the nuclear matrix elements which are necessary in the evaluation of the neutrinoless double beta ({beta}{beta}(0v)) decay half-life.

Barea, J. [Instituto de Estructura de la Materia, Consejo Superior de Investigaciones Cientificas, Unidad Asociada al Departamento de Fisica Atomica, Molecular y Nuclear. Facultad de Fisica, Universidad de Sevilla, Apartado 1065, 41080 Sevilla (Spain)

2009-11-09T23:59:59.000Z

448

Efficiency of free energy calculations of spin lattices by spectral quantum algorithms  

E-Print Network [OSTI]

Quantum algorithms are well-suited to calculate estimates of the energy spectra for spin lattice systems. These algorithms are based on the efficient calculation of the discrete Fourier components of the density of states. The efficiency of these algorithms in calculating the free energy per spin of general spin lattices to bounded error is examined. We find that the number of Fourier components required to bound the error in the free energy due to the broadening of the density of states scales polynomially with the number of spins in the lattice. However, the precision with which the Fourier components must be calculated is found to be an exponential function of the system size.

Cyrus P. Master; Fumiko Yamaguchi; Yoshihisa Yamamoto

2002-07-10T23:59:59.000Z

449

Double resonance Raman spectra of graphene : a full 2D calculation  

E-Print Network [OSTI]

Visible range Raman spectra of graphene are generated based on the double resonant process employing a full two-dimensional numerical calculation applying second-order perturbation theory. Tight binding expressions for ...

Narula, Rohit

2007-01-01T23:59:59.000Z

450

An Algorithm for Calculating the Probability of Classes of Data Patterns on a Genealogy  

E-Print Network [OSTI]

Felsenstein’s pruning algorithm allows one to calculate the probability of any particular data pattern arising on a phylogeny given a model of character evolution. Here we present a similar dynamic programming algorithm. ...

Koch, Jordan M.; Holder, Mark T.

2012-12-14T23:59:59.000Z

451

On the calculation rule of probability of relativistic free particle in quantum mechanics  

E-Print Network [OSTI]

As is well known, in quantum mechanics, the calculation rule of the probability that an eigen-value a_n is observed when the physical quantity A is measured for a state described by the state vector |> is P(a_n)= . However, in Ref.[1], based on strict logical reasoning and mathematical calculation, it has been pointed out, replacing , one should use a new rule to calculate P(a_n) for particle satisfying the Dirac equation. In this paper, we first state some results given by Ref.[1]. And then, we present a proof for the new calculation rule of probability according to Dirac sea of negative energy particles, hole theory and the principle "the vacuum is not observable". Finally, we discuss simply the case of particle satisfying the Klein-Gordon equation.

T. Mei

2008-08-05T23:59:59.000Z

452

Algorithm for the calculation of proximity area and area centroid within the carpal joint  

E-Print Network [OSTI]

's corresponding proximity distance and projected bone information to calculate proximity "area" and its centroid. The programs accuracy was tested creating input files from a know geometry and testing the output for different thresholds. Each wrist was analyzed...

Boyd, Nolan Lee

1998-01-01T23:59:59.000Z

453

Parallel Reacting Flow Calculations for Chemical Vapor Deposition Reactor Design 1  

E-Print Network [OSTI]

, memory, and scalability of distributed memory parallel computers. An unstructured finite element transport from the fluid mechanics and heat transfer. Both works used solution procedures that require the reacting flow model and numerical method and summarize representative calculations using MPSalsa

Devine, Karen

454

Calculation of safe parameters of air shock waves for underwater explosions  

SciTech Connect (OSTI)

The paper proposes a functional relationship for the calculation of the pressure at an air shock-wave front in underwater explosions of plaster-blasting charges. The maximum permissible mass of the charge and safe distance for objects can be calculated for an assigned value of the critical pressure at the air shock-wave front. The authors also state that this work was conducted as there are practically no significant results of experimental or theoretical investigations of this problem.

Smolii, N.I.; Ganopol'skii, M.I.

1985-07-01T23:59:59.000Z

455

An improved finite difference calculation of downhole dynamometer cards for sucker rod pumps  

E-Print Network [OSTI]

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...

Everitt, Thomas Aaron

1987-01-01T23:59:59.000Z

456

DCHAIN V1.3. Radioactive Decay and Reaction Chain Calculations  

SciTech Connect (OSTI)

DCHAIN calculates the time-dependent daughter populations in radioactive decay and nuclear reaction chains. Chain members can have non-zero initial populations and be produced from the preceding chain member as the result of radioactive decay, a nuclear reaction, or both. Parent-daughter equilibrium times and relative activities at equilibrium can also be calculated. Program input can be supplied interactively or read from ASCII files.

East, L.V. [EG and G Idaho, Inc., Idaho Falls, ID (United States)

1994-04-01T23:59:59.000Z

457

Water Power Calculator Temperature and Analog Input/Output Module Ambient Temperature Testing  

SciTech Connect (OSTI)

Water Power Calculator Temperature and Analog input/output Module Ambient Temperature Testing A series of three ambient temperature tests were conducted for the Water Power Calculator development using the INL Calibration Laboratory’s Tenney Environmental Chamber. The ambient temperature test results demonstrate that the Moore Industries Temperature Input Modules, Analog Input Module and Analog Output Module, ambient temperature response meet or exceed the manufactures specifications

Mark D. McKay

2011-02-01T23:59:59.000Z

458

End-to-end calculation of the radiation characteristics of VVER-1000 spent fuel assemblies  

SciTech Connect (OSTI)

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.

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

459

Properties of the largest fragment in multifragmentation: a canonical thermodynamic calculation  

E-Print Network [OSTI]

Many calculations for the production of light and intermediate particles resulting from heavy ion collisions at intermediate energies exist. Calculations of properties of the largest fragment resulting from multifragmentation are rare. In this paper we compute these properties and compare them with the data for the case of gold on carbon. We use the canonical thermodynamic model. The model also gives a bimodal distribution for the largest fragment in a narrow energy range.

G. Chaudhuri; S. Das Gupta

2007-02-27T23:59:59.000Z

460

Statewide Air Emissions Calculations from Wind and Other Renewables: Summary Report  

E-Print Network [OSTI]

Engineering Experiment Station or the Energy Systems Laboratory. Page August 2009 Energy Systems Laboratory, Texas A&M University System 3 SUMMARY REPORT Statewide Air Emissions Calculations from Wind and Other Renewables 1. EXECUTIVE SUMMARY...). The Energy Systems Laboratory, in fulfillment of its responsibilities under this Legislation, submits its third annual report, ?Statewide Air Emissions Calculations from Wind and Other Renewables,? to the Texas Commission on Environmental Quality...

Chandrasekaran, Vivek; Turner, Dan; Yazdani, Bahman; Culp, Charles; Gilman, Don; Baltazar-Cervantes, Juan-Carlos; Liu, Zi; Haberl, Jeff S.

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


461

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

E-Print Network [OSTI]

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

S. M. Bilenky; J. A. Grifols

2002-07-23T23:59:59.000Z

462

Calculation of conventional and prompt lepton fluxes at very high energy  

E-Print Network [OSTI]

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.

Fedynitch, Anatoli; Gaisser, Thomas K; Riehn, Felix; Stanev, Todor

2015-01-01T23:59:59.000Z

463

Title and author(s) REMI/HEAT COOL A COMPUTER PROGRAMME FOR CALCULATION  

E-Print Network [OSTI]

/tøEAT COOL, which is part of a set of programmes, aimed at the calculation of the reactor core responseTitle and author(s) REMI/HEAT COOL A COMPUTER PROGRAMME FOR CALCULATION OF CORE HEAT UP WITH 3PRAY COOLING. by ·Jens Andersen Henning Abel-Larsen O a t ^ktobber VV Y Department or group Reactor Physic

464

Dealing with parameter uncertainty in the calculation of water surface profiles  

E-Print Network [OSTI]

ABSTRACT Dealing with Parameter Uncertainty in the Calculation of Water Surface Profiles. (August 1998) Ruben R Vargas-Cruz, B. S. , Polytechnic University of Puerto Rico Chair of Advisory Committee: Dr. Ralph A. Wurbs Hydrologic and hydraulic... component of the hydrologic cycle in the analysis is important. In that case the water budget must be calculated using the following expression. P ? R ? I ? G ? E ? T=tkS where, P = Precipitation, R = Surface runoff, I = Infiltration, G = Groundwater...

Vargas-Cruz, Ruben F.

1998-01-01T23:59:59.000Z

465

Calculating Energy and Demand Retrofit Savings for Victoria High School: Interim Report  

E-Print Network [OSTI]

ESL-TR-92/12-03 Calculating Energy and Demand Retrofit Savings For Victoria High School Yue Liu, T. Agami Reddy, S. Katipamula and David E. Claridge. Interim Report Energy Systems Laboratory Texas A&M University College Station, TX 77843 December... 1992 Calculating Energy and Demand Retrofit Savings For Victoria High School Yue Liu, T. Agami Reddy, S. Katipamula and David E. Claridge. Interim Report Energy Systems Laboratory Texas A&M University College Station, TX 77843 December 1992 Abstract...

Liu, Y.; Reddy, T. A.; Katipamula, S.; Claridge, D. E.

1992-01-01T23:59:59.000Z

466

A hybrid Monte Carlo and response matrix Monte Carlo method in criticality calculation  

SciTech Connect (OSTI)

Full core calculations are very useful and important in reactor physics analysis, especially in computing the full core power distributions, optimizing the refueling strategies and analyzing the depletion of fuels. To reduce the computing time and accelerate the convergence, a method named Response Matrix Monte Carlo (RMMC) method based on analog Monte Carlo simulation was used to calculate the fixed source neutron transport problems in repeated structures. To make more accurate calculations, we put forward the RMMC method based on non-analog Monte Carlo simulation and investigate the way to use RMMC method in criticality calculations. Then a new hybrid RMMC and MC (RMMC+MC) method is put forward to solve the criticality problems with combined repeated and flexible geometries. This new RMMC+MC method, having the advantages of both MC method and RMMC method, can not only increase the efficiency of calculations, also simulate more complex geometries rather than repeated structures. Several 1-D numerical problems are constructed to test the new RMMC and RMMC+MC method. The results show that RMMC method and RMMC+MC method can efficiently reduce the computing time and variations in the calculations. Finally, the future research directions are mentioned and discussed at the end of this paper to make RMMC method and RMMC+MC method more powerful. (authors)

Li, Z.; Wang, K. [Dept. of Engineering Physics, Tsinghua Univ., Beijing, 100084 (China)

2012-07-01T23:59:59.000Z

467

Estimates of Columbia River radionuclide concentrations: Data for Phase 1 dose calculations  

SciTech Connect (OSTI)

Pacific Northwest Laboratory is conducting the Hanford Environmental Dose Reconstruction Project to estimate the radiation doses people may have received from historical Hanford Site operations. Under the direction of an independent Technical Steering Panel, the project is being conducted in phases. The objective of the first phase is to assess the feasibility of the project-wide technical approach for acquiring data and developing models needed to calculate potential radiation doses. This report summarizes data that were generated for the Phase 1 dose calculations. These included monthly average concentrations of specific radionuclides in Columbia River water and sediments between Priest Rapids Dam and McNary Dam for the years 1964 to 1966. Nine key radionuclides were selected for analysis based on estimation of their contribution to dose. Concentrations of these radionuclides in the river were estimated using existing measurements and hydraulic calculations based on the simplifying assumption that dilution and decay were the primary processes controlling the fate of radionuclides released to the river. Five sub-reaches between Priest Rapids Dam and McNary Dam, corresponding to population centers and tributary confluences, were identified and monthly average radionuclide concentrations were calculated for each sub-reach. The hydraulic calculations were performed to provide radionuclide concentration estimates for time periods and geographic locations where measured data were not available. The validity of the calculation method will be evaluated in Phase 2. 12 refs., 13 figs., 49 tabs.

Richmond, M.C.; Walters, W.H.

1991-05-01T23:59:59.000Z

468

The Development of the GCPCC Protein Crystallography Beamline at CAMD  

E-Print Network [OSTI]

as a simple synchrotron with a bending radius of 0.71 meters. For heat-load calculations, all five wiggler heat load on the first monochromator crystal by acting as a low pass filter. The wavelength is selected. The beamline design, with supporting calculations and ray tracing, is presented to substantiate the expected

Phillips, George N. Jr.

469

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

SciTech Connect (OSTI)

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

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

2012-07-01T23:59:59.000Z

470

Lung Dose Calculation With SPECT/CT for {sup 90}Yittrium Radioembolization of Liver Cancer  

SciTech Connect (OSTI)

Purpose: To propose a new method to estimate lung mean dose (LMD) using technetium-99m labeled macroaggregated albumin ({sup 99m}Tc-MAA) single photon emission CT (SPECT)/CT for {sup 90}Yttrium radioembolization of liver tumors and to compare the LMD estimated using SPECT/CT with clinical estimates of LMD using planar gamma scintigraphy (PS). Methods and Materials: Images of 71 patients who had SPECT/CT and PS images of {sup 99m}Tc-MAA acquired before TheraSphere radioembolization of liver cancer were analyzed retrospectively. LMD was calculated from the PS-based lung shunt assuming a lung mass of 1 kg and 50 Gy per GBq of injected activity shunted to the lung. For the SPECT/CT-based estimate, the LMD was calculated with the activity concentration and lung volume derived from SPECT/CT. The effect of attenuation correction and the patient's breathing on the calculated LMD was studied with the SPECT/CT. With these effects correctly taken into account in a more rigorous fashion, we compared the LMD calculated with SPECT/CT with the LMD calculated with PS. Results: The mean dose to the central region of the lung leads to a more accurate estimate of LMD. Inclusion of the lung region around the diaphragm in the calculation leads to an overestimate of LMD due to the misregistration of the liver activity to the lung from the patient's breathing. LMD calculated based on PS is a poor predictor of the actual LMD. For the subpopulation with large lung shunt, the mean overestimation from the PS method for the lung shunt was 170%. Conclusions: A new method of calculating the LMD for TheraSphere and SIR-Spheres radioembolization of liver cancer based on {sup 99m}Tc-MAA SPECT/CT is presented. The new method provides a more accurate estimate of radiation risk to the lungs. For patients with a large lung shunt calculated from PS, a recalculation of LMD based on SPECT/CT is recommended.

Yu, Naichang, E-mail: yun@ccf.org [Department of Radiation Oncology, Cleveland Clinic, Cleveland, OH (United States)] [Department of Radiation Oncology, Cleveland Clinic, Cleveland, OH (United States); Srinivas, Shaym M.; DiFilippo, Frank P.; Shrikanthan, Sankaran [Department of Nuclear Medicine, Cleveland Clinic, Cleveland, OH (United States)] [Department of Nuclear Medicine, Cleveland Clinic, Cleveland, OH (United States); Levitin, Abraham; McLennan, Gordon; Spain, James [Department of Interventional Radiology, Cleveland Clinic, Cleveland, OH (United States)] [Department of Interventional Radiology, Cleveland Clinic, Cleveland, OH (United States); Xia, Ping; Wilkinson, Allan [Department of Radiation Oncology, Cleveland Clinic, Cleveland, OH (United States)] [Department of Radiation Oncology, Cleveland Clinic, Cleveland, OH (United States)

2013-03-01T23:59:59.000Z

471

Calculated criticality for sup 235 U/graphite systems using the VIM Monte Carlo code  

SciTech Connect (OSTI)

Calculations for highly enriched uranium and graphite systems gained renewed interest recently for the new production modular high-temperature gas-cooled reactor (MHTGR). Experiments to validate the physics calculations for these systems are being prepared for the Transient Reactor Test Facility (TREAT) reactor at Argonne National Laboratory (ANL-West) and in the Compact Nuclear Power Source facility at Los Alamos National Laboratory. The continuous-energy Monte Carlo code VIM, or equivalently the MCNP code, can utilize fully detailed models of the MHTGR and serve as benchmarks for the approximate multigroup methods necessary in full reactor calculations. Validation of these codes and their associated nuclear data did not exist for highly enriched {sup 235}U/graphite systems. Experimental data, used in development of more approximate methods, dates back to the 1960s. The authors have selected two independent sets of experiments for calculation with the VIM code. The carbon-to-uranium (C/U) ratios encompass the range of 2,000, representative of the new production MHTGR, to the ratio of 10,000 in the fuel of TREAT. Calculations used the ENDF/B-V data.

Collins, P.J.; Grasseschi, G.L.; Olsen, D.N. (Argonne National Lab.-West, Idaho Falls (United States)); Finck, P.J. (Argonne National Lab., IL (United States))

1992-01-01T23:59:59.000Z

472

The Dirac equation in electronic structure calculations: Accurate evaluation of DFT predictions for actinides  

SciTech Connect (OSTI)

Brooks, Johansson, and Skriver, using the LMTO-ASA method and considerable insight, were able to explain many of the ground state properties of the actinides. In the many years since this work was done, electronic structure calculations of increasing sophistication have been applied to actinide elements and compounds, attempting to quantify the applicability of DFT to actinides and actinide compounds and to try to incorporate other methodologies (i.e. DMFT) into DFT calculations. Through these calculations, the limits of both available density functionals and ad hoc methodologies are starting to become clear. However, it has also become clear that approximations used to incorporate relativity are not adequate to provide rigorous tests of the underlying equations of DFT, not to mention ad hoc additions. In this talk, we describe the result of full-potential LMTO calculations for the elemental actinides, comparing results obtained with a full Dirac basis with those obtained from scalar-relativistic bases, with and without variational spin-orbit. This comparison shows that the scalar relativistic treatment of actinides does not have sufficient accuracy to provide a rigorous test of theory and that variational spin-orbit introduces uncontrolled errors in the results of electronic structure calculations on actinide elements.

Wills, John M [Los Alamos National Laboratory; Mattsson, Ann E [Sandia National Laboratories

2012-06-06T23:59:59.000Z

473

Linearly Scaling 3D Fragment Method for Large-Scale Electronic Structure Calculations  

SciTech Connect (OSTI)

We present a new linearly scaling three-dimensional fragment (LS3DF) method for large scale ab initio electronic structure calculations. LS3DF is based on a divide-and-conquer approach, which incorporates a novel patching scheme that effectively cancels out the artificial boundary effects due to the subdivision of the system. As a consequence, the LS3DF program yields essentially the same results as direct density functional theory (DFT) calculations. The fragments of the LS3DF algorithm can be calculated separately with different groups of processors. This leads to almost perfect parallelization on tens of thousands of processors. After code optimization, we were able to achieve 35.1 Tflop/s, which is 39percent of the theoretical speed on 17,280 Cray XT4 processor cores. Our 13,824-atom ZnTeO alloy calculation runs 400 times faster than a direct DFTcalculation, even presuming that the direct DFT calculation can scale well up to 17,280 processor cores. These results demonstrate the applicability of the LS3DF method to material simulations, the advantage of using linearly scaling algorithms over conventional O(N3) methods, and the potential for petascale computation using the LS3DF method.

Wang, Lin-Wang; Lee, Byounghak; Shan, Hongzhang; Zhao, Zhengji; Meza, Juan; Strohmaier, Erich; Bailey, David H.

2008-07-01T23:59:59.000Z

474

A High-Performance Fortran Code to Calculate Spin- and Parity-Dependent Nuclear Level Densities  

E-Print Network [OSTI]

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.

R. Sen'kov; M. Horoi; V. G. Zelevinsky

2012-06-20T23:59:59.000Z

475

A High-Performance Fortran Code to Calculate Spin- and Parity-Dependent Nuclear Level Densities  

E-Print Network [OSTI]

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.

Sen'kov, R; Zelevinsky, V G

2012-01-01T23:59:59.000Z

476

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

SciTech Connect (OSTI)

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

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

2009-05-01T23:59:59.000Z

477

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

SciTech Connect (OSTI)

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

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

2007-07-01T23:59:59.000Z

478

Building Technologies Program: Tax Deduction Qualified Software- Owens Corning Commercial Energy Calculator (OC-CEC) version 1.1  

Broader source: Energy.gov [DOE]

Provides required documentation that Owens Corning Commercial Energy Calculator (OC-CEC) version 1.1 meets Internal Revenue Code §179D, Notice 2006-52, dated June 2, 2006, for calculating commercial building energy and power cost savings.

479

Ionization potential of {sup 9}Be calculated including nuclear motion and relativistic corrections  

SciTech Connect (OSTI)

Variational calculations employing explicitly correlated Gaussian functions have been performed for the ground states of {sup 9}Be and {sup 9}Be{sup +} including the nuclear motion [i.e., without assuming the Born-Oppenheimer (BO) approximation]. An approach based on the analytical energy gradient calculated with respect to the Gaussian exponential parameters was employed, leading to energies of the two systems noticeably improved over those found in the recent paper of Pachucki and Komasa [Phys. Rev. A 73, 052502 (2006)]. The non-BO wave functions were used to calculate the {alpha}{sup 2} relativistic corrections ({alpha}=e{sup 2}/({Dirac_h}/2{pi})c). With those corrections and the {alpha}{sup 3} and {alpha}{sup 4} corrections taken from Pachucki and Komasa, a new value of the ionization potential (IP) of {sup 9}Be was determined. It agrees very well with the most recent experimental IP.

Stanke, Monika [Department of Chemistry, University of Arizona, Tucson, Arizona 85721 (United States); Institute of Physics, Nicholas Copernicus University, ulica Grudziadzka 5, PL 87-100 Torun (Poland); Kedziera, Dariusz [Department of Chemistry, Nicholas Copernicus University, ulica Gagarina 7, PL 87-100 Torun (Poland); Bubin, Sergiy [Department of Chemistry, University of Arizona, Tucson, Arizona 85721 (United States); Adamowicz, Ludwik [Department of Chemistry, University of Arizona, Tucson, Arizona 85721 (United States); Department of Physics, University of Arizona, Tucson, Arizona 85721 (United States)

2007-05-15T23:59:59.000Z

480

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

SciTech Connect (OSTI)

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

Zhu, G.; Lewandowski, A.

2012-11-01T23:59:59.000Z

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481

Molecular dynamics (MD) calculation of the real zeta potential of neutral surfaces  

E-Print Network [OSTI]

Molecular dynamics (MD) simulations of the zeta potential are so poor that it has become common to term their predictions "apparent". Here we demonstrate how MD methods can predict zeta potentials accurate enough they can be termed "real". The critical new aspects of our method are: (1) integrating the net average charge in surface-parallel layers from the midpoint of the fluid layer (where the electrostatic potential is zero) to and then into two solid caps, (2) determining the position of slipping plane with separate Couette flow models, and (3) calculating the charge distribution and electrostatic potential under static conditions. The solids are charge neutral surfaces composed of atoms with zero charge or charge balanced monovalent or divalent ions. The zeta potentials calculated are within a few millivolts of measured values, and the measured values fall within the simulation error bars. The zeta potentials calculated with the Helmholtz and Smoluchowski equation following current practice are 10's of mi...

Liu, Hongyi

2013-01-01T23:59:59.000Z

482

Comparison of Spectroscopic Data with Cluster Calculations of Plutonium, Plutonium Dioxide and Uranium Dioxide  

SciTech Connect (OSTI)

Using spectroscopic data produced in the experimental investigations of bulk systems, including X-Ray Absorption Spectroscopy (XAS), Photoelectron Spectroscopy (PES) and Bremstrahlung Isochromat Spectroscopy (BIS), the theoretical results within for UO{sub 2}{sup 6}, PuO{sub 2}{sup 6} and Pu{sup 7} clusters have been evaluated. The calculations of the electronic structure of the clusters have been performed within the framework of the Relativistic Discrete-Variational Method (RDV). The comparisons between the LLNL experimental data and the Russian calculations are quite favorable. The cluster calculations may represent a new and useful avenue to address unresolved questions within the field of actinide electron structure, particularly that of Pu. Observation of the changes in the Pu electronic structure as a function of size suggests interesting implications for bulk Pu electronic structure.

Tobin, J G; Yu, S W; Chung, B W; Ryzhkov, M V; Mirmelstein, A

2012-05-15T23:59:59.000Z

483

Determination of Godiva`s effective delayed neutron fraction using newly calculated delayed neutron spectra  

SciTech Connect (OSTI)

When calculating the effective delayed neutron fraction {beta}{sub eff} for a given reactor system, the assumed delayed neutron group spectra and the assumed number of delayed neutrons born per fission {nu}{sub d} can have a major impact on the final value. Over the years, the recommended values for the delayed neutron spectra and for {nu}{sub d} have slowly changed. To ascertain whether or not these changes have increased the accuracy of {beta}{sub eff} calculations in fast {sup 235}U systems, the authors have reevaluated {beta}{sub eff} for the benchmark system Godiva-I using newly calculated delayed neutron spectra and Tuttle`s recommended values of {nu}{sub d} for both {sup 235}U and {sup 238}U.

Spriggs, G.D.; Campbell, J.M. [Los Alamos National Lab., NM (United States); Busch, R.D. [Univ. of New Mexico, Albuquerque, NM (United States)

1999-09-01T23:59:59.000Z

484

Model for incorporating fuel swelling and clad shrinkage effects in diffusion theory calculations (LWBR Development Program)  

SciTech Connect (OSTI)

A model has been devised for incorporating into the thermal feedback procedure of the PDQ few-group diffusion theory computer program the explicit calculation of depletion and temperature dependent fuel-rod shrinkage and swelling at each mesh point. The model determines the effect on reactivity of the change in hydrogen concentration caused by the variation in coolant channel area as the rods contract and expand. The calculation of fuel temperature, and hence of Doppler-broadened cross sections, is improved by correcting the heat transfer coefficient of the fuel-clad gap for the effects of clad creep, fuel densification and swelling, and release of fission-product gases into the gap. An approximate calculation of clad stress is also included in the model.

Schick, W.C. Jr.; Milani, S.; Duncombe, E.

1980-03-01T23:59:59.000Z

485

An iterative calculation for determining formation and fracture properties in hydraulically fractured reservoirs  

E-Print Network [OSTI]

L 6. Calculate xf . . 0 . 0002637 kt f $ p. c. D 7. Calculate tD 0. 0002637 k (/it max) a D 2 ~golgi 'g' xf 8. Find kt/k from Figure 6 using tD and C . a D r' 9. Calculate a new value for k: kt = (kt/k ) x k 10. Repeat (2) through (10...D, versus the square root of dimensionless time, ~tD, where*: k h (p. ? p f) D 1412 q B. p. g g~ P and 0. 0002637 k 'D- 2 fl . c . Xf Data have been graphed for several values of dimensionless fracture conductivity, C, which is defined as: r' w kf...

Gist, Stephen Rhett

1984-01-01T23:59:59.000Z

486

Project W-320, 241-C-106 sluicing: Piping calculations. Volume 4  

SciTech Connect (OSTI)

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.

Bailey, J.W.

1998-07-24T23:59:59.000Z

487

Calculating a checksum with inactive networking components in a computing system  

DOE Patents [OSTI]

Calculating a checksum utilizing inactive networking components in a computing system, including: identifying, by a checksum distribution manager, an inactive networking component, wherein the inactive networking component includes a checksum calculation engine for computing a checksum; sending, to the inactive networking component by the checksum distribution manager, metadata describing a block of data to be transmitted by an active networking component; calculating, by the inactive networking component, a checksum for the block of data; transmitting, to the checksum distribution manager from the inactive networking component, the checksum for the block of data; and sending, by the active networking component, a data communications message that includes the block of data and the checksum for the block of data.

Aho, Michael E; Chen, Dong; Eisley, Noel A; Gooding, Thomas M; Heidelberger, Philip; Tauferner, Andrew T

2014-12-16T23:59:59.000Z

488

Improved Coefficient Calculator for the California Energy Commission 6 Parameter Photovoltaic Module Model  

SciTech Connect (OSTI)

This paper describes an improved algorithm for calculating the six parameters required by the California Energy Commission (CEC) photovoltaic (PV) Calculator module model. Rebate applications in California require results from the CEC PV model, and thus depend on an up-to-date database of module characteristics. Currently, adding new modules to the database requires calculating operational coefficients using a general purpose equation solver - a cumbersome process for the 300+ modules added on average every month. The combination of empirical regressions and heuristic methods presented herein achieve automated convergence for 99.87% of the 5487 modules in the CEC database and greatly enhance the accuracy and efficiency by which new modules can be characterized and approved for use. The added robustness also permits general purpose use of the CEC/6 parameter module model by modelers and system analysts when standard module specifications are known, even if the module does not exist in a preprocessed database.

Dobos, A. P.

2012-05-01T23:59:59.000Z

489

Intact and Degraded Component Criticality Calculations of N Reactors Spent Nuclear Fuel  

SciTech Connect (OSTI)

The objective of this calculation is to perform intact and degraded mode criticality evaluations of the Department of Energy's (DOE) N Reactor Spent Nuclear Fuel codisposed in a 2-Defense High-Level Waste (2-DHLW)/2-Multi-Canister Overpack (MCO) Waste Package (WP) and emplaced in a monitored geologic repository (MGR) (see Attachment I). The scope of this calculation is limited to the determination of the effective neutron multiplication factor (k{sub eff}) for both intact and degraded mode internal configurations of the codisposal waste package. This calculation will support the analysis that will be performed to demonstrate the technical viability for disposing of U-metal (N Reactor) spent nuclear fuel in the potential MGR.

L. Angers

2001-01-31T23:59:59.000Z

490

Ab initio calculations on magnetism induced by composite defects in magnesium oxide  

SciTech Connect (OSTI)

The local magnetic state induced by the composite defects, composed of an oxygen vacancy and a nitrogen substituting oxygen, in magnesium oxide has been studied by using ab initio calculation based on density functional theory. The calculated results show that local magnetic moment can be induced by the composite defects around the oxygen vacancy, when the exchange split of the oxygen vacancy is enhanced either by the hybridization between the N-p and nearest neighbor O-p orbitals or by applying on-site Coulomb repulsion (U) and exchange interaction (J). We show that the magnetic state induced by the composite defect is energetically more stable than the non-magnetic state. In addition, we show that the U and J applied on the p-orbitals of N and O atoms may significantly impact the calculated magnetic state of the composite defect, resulting in magnetic state for a configuration that is non-magnetic by generalized gradient approximation.

Zhang, Yao-Fang [Department of Physics, Tianjin Polytechnic University, Tianjin 300384 (China); College of Electronic Information and Optical Engineering, Nankai University, Tianjin 300071 (China); Feng, Min [School of Physics, Nankai University, Tianjin 300071 (China); Shao, Bin [Department of Physics, Tsinghua University, Beijing 100084 (China); Lu, Yuan; Zuo, Xu, E-mail: xzuonku@gmail.com [College of Electronic Information and Optical Engineering, Nankai University, Tianjin 300071 (China); Liu, Hong [Office of International Academic Exchanges, Nankai University, Tianjin 300071 (China)

2014-05-07T23:59:59.000Z

491

A new approach to calculate the transport matrix in RF cavities  

SciTech Connect (OSTI)

A realistic approach to calculate the transport matrix in RF cavities is developed. It is based on joint solution of equations of longitudinal and transverse motion of a charged particle in an electromagnetic field of the linac. This field is a given by distribution (measured or calculated) of the component of the longitudinal electric field on the axis of the linac. New approach is compared with other matrix methods to solve the same problem. The comparison with code ASTRA has been carried out. Complete agreement for tracking results for a TESLA-type cavity is achieved. A corresponding algorithm will be implemented into the MARS15 code. A realistic approach to calculate the transport matrix in RF cavities is developed. Complete agreement for tracking results with existed code ASTRA is achieved. New algorithm will be implemented into MARS15 code.

Eidelman, Yu.; /Novosibirsk, IYF; Mokhov, N.; Nagaitsev, S.; Solyak, N.; /Fermilab

2011-03-01T23:59:59.000Z

492

A High-Performance Algorithm to Calculate Spin- and Parity-Dependent Nuclear Level Densities  

E-Print Network [OSTI]

A new algorithm for calculating the spin- and parity-dependent shell model nuclear level densities using the moments method in the proton-neutron formalism is presented. A new, parallelized code based on this algorithm was developed and tested using up to 4000 cores for a set of nuclei from the sd-, pf-, and pf + g9/2 - model spaces. By comparing the nuclear level densities at low excitation energy for a given nucleus calculated in two model spaces, such as pf and pf + g9/2, one could estimate the ground state energy in the larger model space, which is not accessible to direct shell model calculations due to the unmanageable dimension. Examples for the ground state energies of for 64Ge and 68Se in the pf + g9/2 model space are presented.

R. A. Sen'kov; M. Horoi

2010-08-05T23:59:59.000Z

493

A High-Performance Algorithm to Calculate Spin- and Parity-Dependent Nuclear Level Densities  

E-Print Network [OSTI]

A new algorithm for calculating the spin- and parity-dependent shell model nuclear level densities using the moments method in the proton-neutron formalism is presented. A new, parallelized code based on this algorithm was developed and tested using up to 4000 cores for a set of nuclei from the sd-, pf-, and pf + g9/2 - model spaces. By comparing the nuclear level densities at low excitation energy for a given nucleus calculated in two model spaces, such as pf and pf + g9/2, one could estimate the ground state energy in the larger model space, which is not accessible to direct shell model calculations due to the unmanageable dimension. Examples for the ground state energies of for 64Ge and 68Se in the pf + g9/2 model space are presented.

Sen'kov, R A

2010-01-01T23:59:59.000Z

494

Stellar electron-capture rates calculated with the finite-temperature relativistic random-phase approximation  

SciTech Connect (OSTI)

We introduce a self-consistent microscopic theoretical framework for modeling the process of electron capture on nuclei in stellar environment, based on relativistic energy density functionals. The finite-temperature relativistic mean-field model is used to calculate the single-nucleon basis and the occupation factors in a target nucleus, and J{sup {pi}}=0{sup {+-}}, 1{sup {+-}}, and 2{sup {+-}} charge-exchange transitions are described by the self-consistent finite-temperature relativistic random-phase approximation. Cross sections and rates are calculated for electron capture on {sup 54,56}Fe and {sup 76,78}Ge in stellar environment, and results compared with predictions of similar and complementary model calculations.

Niu, Y. F. [State Key Laboratory of Nuclear Physics and Technology, School of Physics, Peking University, Beijing 100871 (China); Paar, N.; Vretenar, D. [Physics Department, Faculty of Science, University of Zagreb, Zagreb (Croatia); Meng, J. [School of Physics and Nuclear Energy Engineering, Beihang University, Beijing 100191 (China); State Key Laboratory of Nuclear Physics and Technology, School of Physics, Peking University, Beijing 100871 (China); Department of Physics, University of Stellenbosch, Stellenbosch 7602 (South Africa)

2011-04-15T23:59:59.000Z

495

Development of a neutronics calculation method for designing commercial type Japanese sodium-cooled fast reactor  

SciTech Connect (OSTI)

Under the R and D project to improve the modeling accuracy for the design of fast breeder reactors the authors are developing a neutronics calculation method for designing a large commercial type sodium- cooled fast reactor. The calculation method is established by taking into account the special features of the reactor such as the use of annular fuel pellet, inner duct tube in large fuel assemblies, large core. The Verification and Validation, and Uncertainty Qualification (V and V and UQ) of the calculation method is being performed by using measured data from the prototype FBR Monju. The results of this project will be used in the design and analysis of the commercial type demonstration FBR, known as the Japanese Sodium fast Reactor (JSFR). (authors)

Takeda, T.; Shimazu, Y.; Hibi, K.; Fujimura, K. [Research Inst. of Nuclear Engineering, Univ. of Fukui, 1cho-me 2gaiku 4, Kanawa-cho, Tsuruga-shi, Fukui 914-0055 (Japan)

2012-07-01T23:59:59.000Z

496

GPU-based acceleration of free energy calculations in solid state physics  

E-Print Network [OSTI]

Obtaining a thermodynamically accurate phase diagram through numerical calculations is a computationally expensive problem that is crucially important to understanding the complex phenomena of solid state physics, such as superconductivity. In this work we show how this type of analysis can be significantly accelerated through the use of modern GPUs. We illustrate this with a concrete example of free energy calculation in multi-band iron-based superconductors, known to exhibit a superconducting state with oscillating order parameter. Our approach can also be used for classical BCS-type superconductors. With a customized algorithm and compiler tuning we are able to achieve a 19x speedup compared to the CPU (119x compared to a single CPU core), reducing calculation time from minutes to mere seconds, enabling the analysis of larger systems and the elimination of finite size effects.

Januszewski, Micha?; Crivelli, Dawid; Gardas, Bart?omiej

2014-01-01T23:59:59.000Z

497

Enrico Fermi Fast Reactor Spent Nuclear Fuel Criticality Calculations: Degraded Mode  

SciTech Connect (OSTI)

The objective of this calculation is to characterize the nuclear criticality safety concerns associated with the codisposal of the Department of Energy's (DOE) Enrico Fermi (EF) Spent Nuclear Fuel (SNF) in a 5-Defense High-Level Waste (5-DHLW) Waste Package (WP) and placed in a Monitored Geologic Repository (MGR). The scope of this calculation is limited to the determination of the effective neutron multiplication factor (k{sub eff}) for the degraded mode internal configurations of the codisposal WP. The results of this calculation and those of Ref. 8 will be used to evaluate criticality issues and support the analysis that will be performed to demonstrate the viability of the codisposal concept for the Monitored Geologic Repository.

D.R. Moscalu; L. Angers; J. Monroe-Rammsey; H.R. Radulesca

2000-07-21T23:59:59.000Z

498

Effective field theory calculation of nd radiative capture at thermal energies  

E-Print Network [OSTI]

The cross section for the thermal neutron capture by the deuteron is calculated with pionless Effective Field Theory(EFT). No new Three-Nucleon forces are needed up to next-to-next-to-leading order in order to achieve cut-off independent results, besides those fixed by the triton binding energy and Nd scattering length in the triton channel. The cross-section is accurately determined to be $\\sigma_{tot}=[0.503\\pm 0.003]mb$. At zero energies, the magnetic $M1$-transition gives the dominant contribution and is calculated up to next-to-next-to-leading order (N$^2$LO). Close agreement between the available experimental data and the calculated cross section is reached. We demonstrate convergence and cutoff independence order by order in the low-energy expansion.

H. Sadeghi; S. Bayegan; Harald W. Griesshammer

2006-12-03T23:59:59.000Z

499

FLUKA calculations of radionuclides, star, and neutron fluence in soil around high-energy electron and proton linear accelerators  

E-Print Network [OSTI]

FLUKA calculations of radionuclides, star, and neutron fluence in soil around high-energy electron and proton linear accelerators

Puryear, A; Rokni, S H

2002-01-01T23:59:59.000Z

500

Introduction au calcul scientifique TP 7 1 http://www.di.ens.fr/~brette/calculscientifique/index.htm  

E-Print Network [OSTI]

. Calculer la hessienne de fi. Implémenter la méthode de Newton pour la minimisation de E (on utilisera les

Brette, Romain