National Library of Energy BETA

Sample records for vertical sonic cross-section

  1. Vertically stabilized elongated cross-section tokamak

    DOE Patents [OSTI]

    Sheffield, George V.

    1977-01-01

    This invention provides a vertically stabilized, non-circular (minor) cross-section, toroidal plasma column characterized by an external separatrix. To this end, a specific poloidal coil means is added outside a toroidal plasma column containing an endless plasma current in a tokamak to produce a rectangular cross-section plasma column along the equilibrium axis of the plasma column. By elongating the spacing between the poloidal coil means the plasma cross-section is vertically elongated, while maintaining vertical stability, efficiently to increase the poloidal flux in linear proportion to the plasma cross-section height to achieve a much greater plasma volume than could be achieved with the heretofore known round cross-section plasma columns. Also, vertical stability is enhanced over an elliptical cross-section plasma column, and poloidal magnetic divertors are achieved.

  2. In situ oil shale retort with a generally T-shaped vertical cross section

    DOE Patents [OSTI]

    Ricketts, Thomas E.

    1981-01-01

    An in situ oil shale retort is formed in a subterranean formation containing oil shale. The retort contains a fragmented permeable mass of formation particles containing oil shale and has a production level drift in communication with a lower portion of the fragmented mass for withdrawing liquid and gaseous products of retorting during retorting of oil shale in the fragmented mass. The principal portion of the fragmented mass is spaced vertically above a lower production level portion having a generally T-shaped vertical cross section. The lower portion of the fragmented mass has a horizontal cross sectional area smaller than the horizontal cross sectional area of the upper principal portion of the fragmented mass above the production level.

  3. 6Li Cross Section

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

    p, X) (Current as of 03012016) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 2004TU02 6Li(p, ): coincidence yields, deduced S-factors low 1, S-factors from ...

  4. 7Li Cross Section

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

    p, X) (Current as of 12162015) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 1997GO13 7Li(pol. p, ): total , S-factor for capture to third-excited state 0 - ...

  5. 9Be Cross Section

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

    9Be(p, X) (Current as of 03012016) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 1997ZA06 9Be(p, ), (p, d): S-factor 16 - 390 keV X4 01232013 1973SI27 9Be(p, ...

  6. 4He Cross Section

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    p, X) (Current as of 03012016) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 1974KR07 4He(p, p): 0.5 - 3 X4 10232014 2004PU02 4He(p, p): ( 128.7) ...

  7. 19F Cross Section

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    p, X) (Incomplete) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 1990WA10 19F(p, n): σ < 30 X4 04/26/2012 2008CO03 19F(p, γ): σ Ecm = 200 - 700 keV X4 05/14/2014 1979SU13 19F(p, γ): σ 0.2 - 1.2 X4 05/06/2014 2006COZY 19F(p, γ1): capture yield 200 - 800 keV thin target 12/08/2014 19F(p, γ): capture yield thick target 19F(p, α2γ): capture yield thin target, thick target 2008CO03 19F(p, γ1): reaction cross section Ecm = 200 - 800 keV thin target, thick target

  8. 10Be Cross Section

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    Be(p, X) (Current as of 03/01/2016) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 1970GO04 10Be(p, γ0): σ 0.6 - 6.3 θ = 0°, θ = 90° 06/05/2012 1987ERZY 10Be(p, n): σ 0.9 - 2 X4 05/15/2012 The following references may be related but not included. 1991GOZV Back to (p, X) Main Page Back to (α, X) Main Page Back to Datacomp Home Page Last modified: 02 March 2016

  9. 6Li Cross Section

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

    α, X) (Current as of 02/01/2016) NSR Reaction Eα (MeV) Cross Section File X4 Dataset Date Added 1985NE05 6Li(α, γ): γ thick target yield resonance X4 02/15/2012 1966FO05 6Li(α, γ): σ 0.9 - 3.0 2 < Eγ < 4 MeV, 4 < Eγ < 7 MeV, thick target capture γ-ray yield, capture γ-ray yield of 2.43 MeV resonance 02/29/2012 1989BA24 6Li(α, γ): σ 1.085, 1.175 X4 02/15/2012 1979SP01 6Li(α, γ): thick target yield curve for 718 keV γ-rays 1140 - 1250 keV 1175 keV resonance 07/19/2011

  10. 19F Cross Section

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    α, X) (Current as of 02/08/2016) NSR Reaction Eα (MeV) Cross Section File X4 Dataset Date Added 2008UG01 19F(α, p): yield curves, σ 792 - 1993 keV X4 09/14/2011 2005UG04 19F(α, p1γ): excitation curve 1238 - 2009 keV 1 11/30/2011 19F(α, p0): excitation curve 1 19F(α, p1): excitation curve 1 1984CS01 19F(α, α): σ 1.5 - 3.7 X4 09/14/2011 1994CH36 19F(α, α): σ 1.5 - 4.5 X4 09/14/2011 2000WR01 19F(α, n): neutron yields and σ 2.28 - 3.10 X4 09/14/2011 1977VA10 19F(α, n): differential

  11. 20Ne Cross Section

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

    p, X) (Current as of 05/15/2012) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 1981DY03 20Ne(p, p'γ): σ for production of γ-rays threshold - 23 1.63-MeV γ-rays X4 03/15/2011 20Ne(p, pαγ): σ for production of γ-rays threshold - 23 6.13-MeV γ-rays 1975RO08 20Ne(p, γ): S-factors 0.37 - 2.10 Direct Capture (DC) → 332-keV state, DC → 2425-keV state, tail of 2425-keV state X4 04/19/2011 20Ne(p, γ): differential σ at θγ = 90° DC → 332-keV state, 332-keV state →

  12. 10B Cross Section

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    α, X) (Current as of 01/21/2015) NSR Reaction Eα (MeV) Cross Section File X4 Dataset Date Added 1992MC03 10B(α, α): σ relative to Rutherford scattering 1 - 3.3 X4 05/02/2012 1969GA01 10B(α, p), (α α'): relative σ at θ = 90° for Eγ = 1.0 - 3.5 0.170 MeV, 3.088 MeV, 3.682 MeV, 3.852 MeV, 0.717 MeV 06/18/2012 1973VA25 10B(α, n): laboratory differential σ 1.0 - 5.0 for n0: θ = 0°, θ = 90°, θ = 160° X4 04/04/2011 for n1: θ = 0°, θ = 90° for n23: θ = 0°, θ = 90° 10B(α, n):

  13. 11B Cross Section

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    B(α, X) (Current as of 02/01/2016) NSR Reaction Eα (MeV) Cross Section File X4 Dataset Date Added 1991WA02 11B(α, n): thick-target yield of Eα = 411, 605 and 606 keV resonance 350 - 2400 keV 1 X4 04/04/2011 11B(α, n): for 606-keV resonance 1 11B(α, n): for 411-keV resonance after subtraction of the 605-keV resonance 1 11B(α, n): S-factor 1 11B(α, n): S-factor for thick-target 400 - 500 keV 1 11B(α, n): S-factor for thin-target 1 1966MA04, Errata 11B(α, n): excitation curve < 4.5 for

  14. 11C Cross Section

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    C(p, X) (Current as of 03/01/2016) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 2013SO11 11C(p, γ): deduced astrophysical reaction rates and S-factors X4 12/14/2015 2003LI51 11C(p, γ): deduced S-factor low X4 09/12/2011 2003TA02 11C(p, γ): deduced S-factor 0 - 0.7 X4 09/12/2011 2003KU36 11C(p, p): elastic scattering σ ~ 0.2 - 3.2 θcm = 180° 09/08/2011 Back to (p, X) Main Page Back to (α, X) Main Page Back to Datacomp Home Page Last modified: 02 March

  15. 12C Cross Section

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    p, X) (Current as of 05/15/2012) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 2001NE15 12C(p, γ): σ, deduced S(E) ratio < 160 keV X4 10/28/2014 1993CH02 12C(p, X): σ for η production ≤ 0.9 GeV X4 03/07/2012 1974RO29 12C(p, γ): σ 150 - 3000 keV X4 08/27/2013 1951GO1B 12C(p, p): yield curve of elastic scattering 0.2 - 4.0 θ = 164° 11/05/2014 1976ME22 12C(p, p): absolute σ 0.3 - 2.0 X4 08/07/2013 2008BU19 12C(p, γ): σ, deduced S-factors. 354, 390, 460, 463, 565,

  16. 13C Cross Section

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    p, X) (Current as of 03/01/2016) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 2001NE15 13C(p, γ): σ, deduced S(E) ratio < 160 keV X4 09/12/2011 1994KI02 13C(p, γ): γ-ray yield, calculated S(E) 120 - 950 keV X4 09/12/2011 2008HE11 13C(p, γ): reaction yield at the resonance 448.5-keV for a fresh target and after an integrated charge of 1C 435 - 470 keV σ X4 11/07/2011 1991BR19 13C(p, γ): reaction yield near the resonance 0.44 - 0.6 483.3-keV, 0.55-MeV X4 11/07/2011

  17. 13C Cross Section

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    α, X) (Current as of 02/08/2016) NSR Reaction Eα (MeV) Cross Section File X4 Dataset Date Added 2006JO11 13C(α, n): deduced S(E) ~ 0 - 1 from (1993BR17), from (1993DR08) X4 08/04/2011 2001HE22 13C(α, n): S(E) 0 - 2 S-factor 11/15/2011 2003KA51 13C(α, n): deduced S-factors, reaction rate Ecm ~ 200 - 800 keV X4 05/01/2012 1993DR08 13C(α, n): excitation function and S(E) ~ 275 - 1075 keV σ, S-factor X4 08/04/2011 2008HE11 13C(α, n): σ, reaction yields and S(E) Ecm = 320 - 700 keV σ, Table

  18. 14N Cross Section

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    p, X) (Incomplete) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 2003MU12 14N(p, γ): deduced astrophysical S-factors < 600 keV X4 05/06/2013 1990WA10 14N(p, n): σ < 30 X4 04/26/2012 2005CO16, 2006BE50 14N(p, γ): σ, deduced astrophysical S-factors, resonance strength 70 - 228 keV X4 05/08/2013 2006LE13 14N(p, γ): σ, deduced astrophysical S-factors 70 - 228 keV X4 05/30/2013 2005BR04, 2005BR15 14N(p, γ): astrophysical S-factors ~ 0.1 - 2.5 1 08/15/2013 2004FO02,

  19. 14N Cross Section

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

    α, X) (Current as of 05/14/2012) NSR Reaction Eα (MeV) Cross Section File X4 Dataset Date Added 1971CO27 14N(α, γ): thick target yield 0.5 - 1.2 1 08/04/2011 2000GO43 14N(α, γ): resonance yields, deduced astrophysical reaction rates 550 - 1300 keV X4 03/01/2012 1973RO03 14N(α, γ): γ-ray yield 1.0 - 3.2 1 04/30/2012 1980MA26 14N(α, α): σ 1.5, 1.6 X4 03/01/2012 2007CH25 14N(α, γ): deduced resonance parameters 1620 - 1775 keV X4 03/01/2012 1994YE11 14N(α, α): σ(θ)/σ(Rutherford) 2

  20. 16O Cross Section

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

    p, X) (Incomplete) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 1973MC12 16O(p, α): σ threshold - 7.7 X4 10/17/2012 1981DY03 16O(p, pα): σ for production of γ-rays threshold - 23 4.44-MeV γ-rays X4 03/15/2011 16O(p, p'): σ for production of γ-rays threshold - 23 6.13-MeV γ-rays 1997MO27 16O(p, p), (p, γ): elastic, capture σ Ecm = 200 - 3750 keV X4 03/28/2013 1973RO34 16O(p, γ): S(E) 0.3 - 3.1 S-Factor X4 05/10/2011 16O(p, γ): differential σ for the DC → ground

  1. 18O Cross Section

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    α, X) (Current as of 05/14/2012) NSR Reaction Eα (MeV) Cross Section File X4 Dataset Date Added 2003DA19 18O(α, γ): deduced resonance strengths ~ 470 - 770 keV X4 02/13/2012 1978TR05 18O(α, γ): excitation function for the 1.27 MeV secondary γ-ray transition 0.6 - 2.3 θγ = 0° 02/29/2012 1990VO06 18O(α, γ): resonance γ yields < 0.78 X4 02/13/2012 1973BA10 18O(α, n): σ with target thickness 1 - 5 6 keV, 13 keV 06/06/2011 1956BO61 18O(α, n): neutron yields 1.8 - 5.3 0° - 30° X4

  2. 3H Cross Section

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

    3H(α, X) (Current as of 02/01/2016) NSR Reaction Eα (MeV) Cross Section File X4 Dataset Date Added 2001TO07 3H(α, γ): deduced S-factor Ecm = 0.05 - 0.8 X4 01/09/2012 1994BR25 3H(α, γ): deduced σ and S-factor Ecm = 50 - 1200 keV X4 01/09/2012 1987SC18 3H(α, γ): σ, deduced S-factor Ecm = 79 - 464 keV X4 01/09/2012 1988SA13 3H(α, α): recoil σ 0.5 - 2.5 X4 01/09/2012 1987BU18 3H(α, γ): σ and S-factor 0.7 - 2 X4 01/09/2012 1968IV01 3H(α, α): elastic scattering σ 3 - 11 Table 9 X4

  3. 3He Cross Section

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    α, X) (Current as of 05/14/2012) NSR Reaction Eα (MeV) Cross Section File X4 Dataset Date Added 1982KR05 3He(α, γ): σ Ecm = 107 - 1266 keV X4 01/05/2012 1969NA24 3He(α, γ): σ and S-factor 164 - 245 keV σ, S(E) X4 07/19/2011 1984OS03 3He(α, γ): σ 165 - 1169 keV X4 01/05/2012 1982OS02 3He(α, γ): S-factor 165 - 1170 keV S34(Ecm) X4 07/19/2011 1988HI06 3He(α, γ): σ Ecm = 195 - 686 keV X4 01/05/2012 2007CO17 3He(α, γ): deduced σ and S-factor 220, 250, 400 keV X4 01/05/2012

  4. 20Ne Cross Section

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    20Ne(α, X) (Current as of 02/08/2016) NSR Reaction Eα (MeV) Cross Section File X4 Dataset Date Added 1983SC17 20Ne(α, γ): deduced S-factor of capture σ 0.55 - 3.2 X4 09/15/2011 1997WI12 20Ne(α, γ): deduced primary transitions yield 1.64 - 2.65 X4 09/15/2011 1999KO34 20Ne(α, γ): γ-ray yield for the transition 1.9 - 2.8 g.s. 01/03/2012 1369 keV g.s. 10917 keV g.s., 1369 keV 11016 keV g.s. 1975KU06 20Ne(α, γ): σ 2.5 - 20 X4 09/15/2011 1968HI02 20Ne(α, γ): σ 3 - 6 X4 09/15/2011

  5. 10B Cross Section

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    p, X) (Current as of 05/15/2012) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 2010LA11 10B(p, α): deduced S(E) E(cm) = 0 - 0.15 1 11/30/2011 1993AN06 10B(p, α): α yield E(cm) = 17 - 134 keV X4 11/07/2011 1993AN09 10B(p, α): absolute fusion σ and S(E) E(cm) = 48 - 159 keV X4 11/07/2011 1972SZ02 10B(p, α): total reaction σ and S(E) 60 - 180 keV 1 X4 03/03/2011 1983WI09 10B(p, γ): γ yield, capture σ(E) 0.07 - 2.2 X4 11/07/2011 2003TO21 10B(pol. p, γ): σ, deduced

  6. 11B Cross Section

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    p, X) (Current as of 12/17/2015) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 2004RO27, 2004SP03 11B(p, α): deduced σ, S-factor Ecm ~ 0 - 1 X4 11/07/2012 2010LA11 11B(p, α): deduced S-factor E(cm) = 0 - 0.6 1 11/30/2011 2000KE10 11B(pol. p, γ): σ, deduced S-factor < 100 keV X4 11/07/2012 1993AN06 11B(p, α): α yield E(cm) = 17 - 134 keV X4 11/29/2012 1979DA03 11B(p, 3α): σ 35.4 - 1500 keV X4 07/30/2014 1992CE02 11B(p, γ): deduced S-factor 40 - 180 keV X4 03/07/2012

  7. 12C Cross Section

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    α, X) (Current as of 05/14/2012) NSR Reaction Eα (MeV) Cross Section File X4 Dataset Date Added 2009MA70 12C(α, γ0): σ 0 - 2.27 X4 05/01/2012 2012OU01 12C(α, γ): deduced S-factor Ecm = 0.3 - 3.5 X4 02/12/2015 1997KU18 12C(α, γ): analyzed S-factor Ecm = 0.9 - 3 X4 05/10/2012 1987RE02 12C(α, γ): σ, deduced S-factor 0.94 - 2.84 X4 05/09/2012 2001HA31 12C(α, γ): deduced S-factors Ecm = 0.95 - 2.78 E1, E2 06/18/2012 2001KU09 12C(α, γ): deduced S-factor Ecm = 0.95 - 2.8 X4 05/09/2012

  8. 14C Cross Section

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    C(p, X) (Incomplete) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 1969SI04 14C(p, γ): γ-rays yield for 230 - 690 keV Eγ ≥ 2.8 MeV 08/15/2013 1990GO25 14C(p, γ): σ, deduced S-factor 250 - 740 keV X4 10/28/2014 1968HE12 14C(p, γ): γ-ray yield 0.6 - 2.7 γ0 01/06/2015 1991WA02 14C(p, n): σ 1.0 - 1.55 X4 10/28/2014 1968HA27 14C(p, p): σ at θcm = 1.0 - 2.7 39.2°, 54.7°, 90°, 125.3°, 161.4° 08/15/2013 1971KU01 14C(p, γ0): excitation function at θ = 90° 1.3 - 2.6 1

  9. 15N Cross Section

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    p, X) (Current as of 05/15/2012) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 1990WA10 15N(p, n): σ < 30 X4 04/26/2012 1982RE06 15N(p, α): σ 78 - 810 keV X4 09/12/2011 1979ZY02 15N(p, α0): σ, deduced S-factor 93 - 418 keV X4 09/12/2011 2010LE21, 2013DE03 15N(p, γ): σ, S-factors 130 - 1800 keV X4 05/01/2012 & 02/01/2016 2012IM02 15N(p, γ), (p, αγ): σ, S-factors 0.14 - 1.80 X4 02/01/2016 1974RO37 15N(p, γ), (p, αγ): σ 150 - 2500 keV X4 09/12/2011 1968GO07

  10. 15N Cross Section

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    α, X) (Current as of 05/14/2012) NSR Reaction Eα (MeV) Cross Section File X4 Dataset Date Added 2002WI18 15N(α γ): σ 461 - 2642 keV X4 09/12/2011 1997WI12 15N(α γ): σ 0.65 - 2.65 X4 09/12/2011 1995WI26 15N(α γ): σ 0.67 - 0.69 X4 09/12/2011 1969AI01 15N(α γ): γ-ray excitation curve for 3.0 ≤ Eγ ≤ 7.0 MeV 2.5 - 3.2 1 11/30/2011 1977DI08 15N(α, γ): γ-ray excitation curve near Eα = 3.15 MeV for transitions to 3146 - 3158 keV five low-lying states, 4.65 MeV (13/2+) state

  11. 16O Cross Section

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    6O(α, X) (Current as of 02/08/2016) NSR Reaction Eα (MeV) Cross Section File X4 Dataset Date Added 1971TO06 16O(α, γ): σ 0.85 - 1.8 X4 09/15/2011 1953CA44 16O(α, α): σ 0.94 - 4.0 X4 09/15/2011 1997KU18 16O(α, γ): analyzed S-factor 1 - 3.25 X4 05/10/2012 1980MA27 16O(α, α): σ 1.305 - 1.330; 2.950 - 3.075 X4 02/14/2012 16O(α, γ): σ 1.37, 2.6, 2.9, 3.036 1987HA24 16O(α, γ): σ Ecm = 1.7 - 2.35 X4 02/14/2012 1990LE06 16O(α, α): σ 1.8 - 5 X4 03/12/2011 1985JA17 16O(α, α): σ 2

  12. 17O Cross Section

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

    p, X) (Current as of 05/15/2012) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 2010SE11 17O(p, α): nuclear excitation function 0 - 0.7 1 06/22/2011 1973RO03 17O(p, γ): γ-ray yield 0.15 - 1.4 1 08/01/2012 2015BU02 17O(p, γ): total S(E)-factors 0.17 - 0.53 X4 03/03/2016 2012SC16, 2014DI01 17O(p, γ): σ, deduced S-factors Ecm = 0.2 - 0.4 X4 03/03/2016 1973RO34 17O(p, γ): S(E) 0.3 - 1.9 S-Factor X4 06/22/2011 17O(p, γ): σ for the γ-ray transition 0.94 → 0 MeV 17O(p, γ):

  13. 17O Cross Section

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    α, X) (Current as of 02/08/2016) NSR Reaction Eα (MeV) Cross Section File X4 Dataset Date Added 2013BE11; see also 2012BEZP 17O(α, n), (α, γ): σ, S-factors 0.8 - 2.3 X4 02/12/2015 1973BA10 17O(α, n): neutron yields with target thickness 0.9 - 5.3 ~ 2.5 keV, 6 keV, 13 keV, ~ 35 keV 06/06/2011 1976MC12 17O(α, n1): yield of 1.63-MeV γ's 1.4 - 2.3 θγ = 50° 04/28/2011 17O(α, n0): yield of neutrons θn = 120° 17O(α, n1): yield of 1.63-MeV γ's 1.825 - 1.885 θγ = 0° 05/03/2011 17O(α,

  14. 18O Cross Section

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    8O(p, X) (Current as of 05/15/2012) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 2008LA06 18O(p, α): deduced S-factor Ecm = 0 - 1.5 θα = 46° 12/03/2012 1990CH32 18O(p, α): σ < 2 X4 10/04/2012 1990VO06 18O(p, γ): resonance γ yields < 0.22 X4 02/13/2012 2008LA13 18O(p, α): deduced σ 0 - 250 keV X4 10/20/2014 1973BA31 18O(p, n): total neutron-production σ < 5 1 X4 05/10/2011 1990WA10 18O(p, n): σ < 30 X4 04/26/2012 1979LO01 18O(p, α): σ 72 - 935 keV X4

  15. Cross Sections for (p, X)

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

    Cross Sections for (p, X) Reaction for Nuclei A = 3 - 20 Go to the Text Only below if you prefer to view the nuclides in a text list. 20Ne 19F 16O 17O 18O 14N 15N 11C 12C 13C 14C 10B 11B 7Be 9Be 10Be 6Li 7Li 3He 4He Note: Comments, and corrections are welcome. Please email us. List of available cross section data for A = 3 - 20 nuclides: Helium: 3He, 4He Lithium: 6Li, 7Li Beryllium: 7Be, 9Be, 10Be Boron: 10B, 11B Carbon: 11C, 12C, 13C, 14C Nitrogen: 14N, 15N Oxygen: 16O, 17O, 18O Fluorine: 19F

  16. Cross Sections for (α, X)

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

    Cross Sections for (α, X) Reaction for Nuclei A = 3 - 20 Go to the Text Only below if you prefer to view the nuclides in a text list. 20Ne 19F 16O 17O 18O 14N 15N 12C 13C 10B 11B 9Be 10Be 6Li 7Li 3He 4He 3H Note: Comments, and corrections are welcome. Please email us. List of available cross section data for A = 3 - 20 nuclides: Hydrogen: 3H Helium: 3He, 4He Lithium: 6Li, 7Li Beryllium: 9Be, 10Be Boron: 10B, 11B Carbon: 12C, 13C Nitrogen: 14N, 15N Oxygen: 16O, 17O, 18O Fluorine: 19F Neon: 20Ne

  17. Elastic scattering and total cross sections

    SciTech Connect (OSTI)

    Cahn, R.N.

    1990-03-01

    This report discusses concepts of elastic scattering and cross sections of proton-proton interactions. (LSP)

  18. Recommended Dosimetry Cross Section Compendium.

    Energy Science and Technology Software Center (OSTI)

    1994-07-11

    Version 00 The data is recommended for spectrum determination applications and for the prediction of neutron activation of typical radiation sensor materials. The library has been tested for consistency of the cross sections in a wide variety of neutron environments. The results and cautions from this testing have been documented. The data has been interfaced with radiation transport codes, such as TWODANT-SYS (CCC-547) and MCNP (CCC-200), in order to compare calculated and measured activities formore » benchmark reactor experiments.« less

  19. Electron Photon Interaction Cross Sections

    Energy Science and Technology Software Center (OSTI)

    2014-11-01

    Version 00 The Electron Photon Interaction Cross Sections, EPICS, provides the atomic data needed to perform coupled Electron-Photon transport calculations, to produce accurate macroscopic results, such as energy deposit and dose. Atomic data is provided for elements, Z = 1 to 100, over the energy range 10 eV to 100 GeV; note that nuclear data, such as photo-nuclear, and data for compounds, are not included. All data is in a simple computer independent text formatmore » that is standard and presented to a high precision that can be easily read by computer codes written in any computer language, e.g., C, C++, and FORTRAN. EPICS includes four separate data bases that are designed to be used in combination, these include, • The Evaluated Electron Data Library (EEDL), to describe the interaction of electrons with matter. • The Evaluated Photon Data Library (EPDL), to describe the interaction of photons with matter. • The Evaluated Atomic Data Library (EADL), to describe the emission of electrons and photons back to neutrality following an ionizing event, caused by either electron or photon interactions. • The Evaluated Excitation Data Library (EXDL), to describe the excitation of atoms due to photon interaction. All of these are available in the Extended ENDL format (ENDLX) in which the evaluations were originally performed. The first three are also available in the ENDF format; as yet ENDF does not include formats to handle excitation data (EXDL).« less

  20. SNL RML recommended dosimetry cross section compendium

    SciTech Connect (OSTI)

    Griffin, P.J.; Kelly, J.G.; Luera, T.F.; VanDenburg, J.

    1993-11-01

    A compendium of dosimetry cross sections is presented for use in the characterization of fission reactor spectrum and fluence. The contents of this cross section library are based upon the ENDF/B-VI and IRDF-90 cross section libraries and are recommended as a replacement for the DOSCROS84 multigroup library that is widely used by the dosimetry community. Documentation is provided on the rationale for the choice of the cross sections selected for inclusion in this library and on the uncertainty and variation in cross sections presented by state-of-the-art evaluations.

  1. Cross Sections for Electron Collisions with Methane

    SciTech Connect (OSTI)

    Song, Mi-Young Yoon, Jung-Sik; Cho, Hyuck; Itikawa, Yukikazu; Karwasz, Grzegorz P.; Kokoouline, Viatcheslav; Nakamura, Yoshiharu; Tennyson, Jonathan

    2015-06-15

    Cross section data are compiled from the literature for electron collisions with methane (CH{sub 4}) molecules. Cross sections are collected and reviewed for total scattering, elastic scattering, momentum transfer, excitations of rotational and vibrational states, dissociation, ionization, and dissociative attachment. The data derived from swarm experiments are also considered. For each of these processes, the recommended values of the cross sections are presented. The literature has been surveyed through early 2014.

  2. MiniBooNE Cross Sections

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

    SSECTIONS(AT)fnal.gov convenors: Alessandro Curioni (alessandro.curioni(AT)yale.edu) and Sam Zeller (gzeller(AT)fnal.gov) Cross Sections at MiniBooNE, Meetings, Reference Articles,...

  3. MODELING AND FISSION CROSS SECTIONS FOR AMERICIUM.

    SciTech Connect (OSTI)

    ROCHMAN, D.; HERMAN, M.; OBLOZINSKY, P.

    2005-05-01

    This is the final report of the work performed under the LANL contract on the modeling and fission cross section for americium isotopes (May 2004-June 2005). The purpose of the contract was to provide fission cross sections for americium isotopes with the nuclear reaction model code EMPIRE 2.19. The following work was performed: (1) Fission calculations capability suitable for americium was implemented to the EMPIRE-2.19 code. (2) Calculations of neutron-induced fission cross sections for {sup 239}Am to {sup 244g}Am were performed with EMPIRE-2.19 for energies up to 20 MeV. For the neutron-induced reaction of {sup 240}Am, fission cross sections were predicted and uncertainties were assessed. (3) Set of fission barrier heights for each americium isotopes was chosen so that the new calculations fit the experimental data and follow the systematics found in the literature.

  4. QuickSite Cross Section Processing

    Energy Science and Technology Software Center (OSTI)

    2003-05-27

    This AGEM-developed system produces cross sections by inputting data in both standard and custom file formats and outputting a graphic file that can be printed or further modified in a commercial graphic program. The system has evolved over several years in order to combine and visualize a changing set of field data more rapidly than was possible with commercially available cross section software packages. It uses some commercial packages to produce the input and tomore » modify the output files. Flexibility is provided by a dynamic set of programs that are customized to accept varying input and accomodate varying output requirements. There are two basic types of routines: conversion routines and cross section generation routines. The conversion routines convery various data files to logger file format which is compatible with a standard file format for LogPlot 98, a commonly used commercial log plotting program. The cross section routines generate cross sections and apply topography to these cross sections. All of the generation routines produce a standard graphic DXF file, which is the format used in AutoCAD and can then be modified in a number of available graphics programs.« less

  5. IDS-NF Impact of Neutrino Cross Section Impact of Neutrino Cross Section

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

    IDS-NF Impact of Neutrino Cross Section Impact of Neutrino Cross Section Knowledge on Oscillation Knowledge on Oscillation Measurements Measurements M. Sorel, IFIC (CSIC and U. of Valencia) IDS-NF, RAL, Jan 16-17 2008 M. Sorel - IFIC (Valencia U. & CSIC) 2 IDS-NF Neutrino Cross Sections: At What Energies Needed? Superbeams: Solid: T2K Dashed: NovA M. Sorel - IFIC (Valencia U. & CSIC) 3 IDS-NF Neutrino Cross Sections: At What Energies Needed? Superbeams: Solid: T2K Dashed: NovA Beta

  6. Precise neutron inelastic cross section measurements

    SciTech Connect (OSTI)

    Negret, Alexandru

    2012-11-20

    The design of a new generation of nuclear reactors requires the development of a very precise neutron cross section database. Ongoing experiments performed at dedicated facilities aim to the measurement of such cross sections with an unprecedented uncertainty of the order of 5% or even smaller. We give an overview of such a facility: the Gamma Array for Inelastic Neutron Scattering (GAINS) installed at the GELINA neutron source of IRMM, Belgium. Some of the most challenging difficulties of the experimental approach are emphasized and recent results are shown.

  7. Covariance Evaluation Methodology for Neutron Cross Sections

    SciTech Connect (OSTI)

    Herman,M.; Arcilla, R.; Mattoon, C.M.; Mughabghab, S.F.; Oblozinsky, P.; Pigni, M.; Pritychenko, b.; Songzoni, A.A.

    2008-09-01

    We present the NNDC-BNL methodology for estimating neutron cross section covariances in thermal, resolved resonance, unresolved resonance and fast neutron regions. The three key elements of the methodology are Atlas of Neutron Resonances, nuclear reaction code EMPIRE, and the Bayesian code implementing Kalman filter concept. The covariance data processing, visualization and distribution capabilities are integral components of the NNDC methodology. We illustrate its application on examples including relatively detailed evaluation of covariances for two individual nuclei and massive production of simple covariance estimates for 307 materials. Certain peculiarities regarding evaluation of covariances for resolved resonances and the consistency between resonance parameter uncertainties and thermal cross section uncertainties are also discussed.

  8. Testing (Validating?) Cross Sections with ICSBEP Benchmarks

    SciTech Connect (OSTI)

    Kahler, Albert C. III

    2012-06-28

    We discuss how to use critical benchmarks from the International Handbook of Evaluated Criticality Safety Benchmark Experiments to determine the applicability of specific cross sections to the end-user's problem of interest. Particular attention is paid to making sure the selected suite of benchmarks includes the user's range of applicability (ROA).

  9. Top quark pair production cross section at Tevatron (Conference...

    Office of Scientific and Technical Information (OSTI)

    Conference: Top quark pair production cross section at Tevatron Citation Details In-Document Search Title: Top quark pair production cross section at Tevatron You are accessing ...

  10. Indirect ( n , γ ) cross sections of thorium cycle nuclei using...

    Office of Scientific and Technical Information (OSTI)

    Indirect ( n , ) cross sections of thorium cycle nuclei using the surrogate method Title: Indirect ( n , ) cross sections of thorium cycle nuclei using the surrogate method ...

  11. New Arsenic Cross Section Calculations (Technical Report) | SciTech...

    Office of Scientific and Technical Information (OSTI)

    New Arsenic Cross Section Calculations Citation Details In-Document Search Title: New Arsenic Cross Section Calculations You are accessing a document from the Department of ...

  12. Estimation of Anisotoropy from Total Cross Section and Optical...

    Office of Scientific and Technical Information (OSTI)

    Conference: Estimation of Anisotoropy from Total Cross Section and Optical Model Citation Details In-Document Search Title: Estimation of Anisotoropy from Total Cross Section and ...

  13. Quality Quantification of Evaluated Cross Section Covariances

    SciTech Connect (OSTI)

    Varet, S.; Dossantos-Uzarralde, P.

    2015-01-15

    Presently, several methods are used to estimate the covariance matrix of evaluated nuclear cross sections. Because the resulting covariance matrices can be different according to the method used and according to the assumptions of the method, we propose a general and objective approach to quantify the quality of the covariance estimation for evaluated cross sections. The first step consists in defining an objective criterion. The second step is computation of the criterion. In this paper the Kullback-Leibler distance is proposed for the quality quantification of a covariance matrix estimation and its inverse. It is based on the distance to the true covariance matrix. A method based on the bootstrap is presented for the estimation of this criterion, which can be applied with most methods for covariance matrix estimation and without the knowledge of the true covariance matrix. The full approach is illustrated on the {sup 85}Rb nucleus evaluations and the results are then used for a discussion on scoring and Monte Carlo approaches for covariance matrix estimation of the cross section evaluations.

  14. Averaging cross section data so we can fit it

    SciTech Connect (OSTI)

    Brown, D.

    2014-10-23

    The 56Fe cross section we are interested in have a lot of fluctuations. We would like to fit the average of the cross section with cross sections calculated within EMPIRE. EMPIRE is a Hauser-Feshbach theory based nuclear reaction code, requires cross sections to be smoothed using a Lorentzian profile. The plan is to fit EMPIRE to these cross sections in the fast region (say above 500 keV).

  15. Cross Sections for Nuclei A = 3 - 20

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

    Cross Sections with Proton and Alpha Induced Reactions for Nuclei A = 3 - 20 I. Introduction: We have scanned the NSR from 1910-present for various articles with proton and alpha induced reactions. We have used the program Plot Digitizer 2.5.0 to extract the excitation functions from figures in the articles. In some cases the uncertainties are provided in the figures, we have noted this in comments, but we have made no attempt to extract the uncertainties. In cases where the data are given in

  16. Actinide Targets for Neutron Cross Section Measurements

    SciTech Connect (OSTI)

    John D. Baker; Christopher A. McGrath

    2006-10-01

    The Advanced Fuel Cycle Initiative (AFCI) and the Generation IV Reactor Initiative have demonstrated a lack of detailed neutron cross-sections for certain "minor" actinides, those other than the most common (235U, 238U, and 239Pu). For some closed-fuel-cycle reactor designs more than 50% of reactivity will, at some point, be derived from "minor" actinides that currently have poorly known or in some cases not measured (n,?) and (n,f) cross sections. A program of measurements under AFCI has begun to correct this. One of the initial hurdles has been to produce well-characterized, highly isotopically enriched, and chemically pure actinide targets on thin backings. Using a combination of resurrected techniques and new developments, we have made a series of targets including highly enriched 239Pu, 240Pu, and 242Pu. Thus far, we have electrodeposited these actinide targets. In the future, we plan to study reductive distillation to achieve homogeneous, adherent targets on thin metal foils and polymer backings. As we move forward, separated isotopes become scarcer, and safety concerns become greater. The chemical purification and electodeposition techniques will be described.

  17. Absolute photoneutron cross sections of Sm isotopes

    SciTech Connect (OSTI)

    Gheorghe, I.; Glodariu, T.; Utsunomiya, H.; Filipescu, D.; Nyhus, H.-T.; Renstrom, T.; Tesileanu, O.; Shima, T.; Takahisa, K.; Miyamoto, S.

    2015-02-24

    Photoneutron cross sections for seven samarium isotopes, {sup 144}Sm, {sup 147}Sm, {sup 148}Sm, {sup 149}Sm, {sup 150}Sm, {sup 152}Sm and {sup 154}Sm, have been investigated near neutron emission threshold using quasimonochromatic laser-Compton scattering γ-rays produced at the synchrotron radiation facility NewSUBARU. The results are important for nuclear astrophysics calculations and also for probing γ-ray strength functions in the vicinity of neutron threshold. Here we describe the neutron detection system and we discuss the related data analysis and the necessary method improvements for adapting the current experimental method to the working parameters of the future Gamma Beam System of Extreme Light Infrastructure - Nuclear Physics facility.

  18. Experiments on Antiprotons: Antiproton-Nucleon Cross Sections

    DOE R&D Accomplishments [OSTI]

    Chamberlain, Owen; Keller, Donald V.; Mermond, Ronald; Segre, Emilio; Steiner, Herbert M.; Ypsilantis, Tom

    1957-07-22

    In this paper experiments are reported on annihilation and scattering of antiprotons in H{sub 2}O , D{sub 2}O, and O{sub 2}. From the data measured it is possible to obtain an antiproton-proton and an antiproton-deuteron cross section at 457 Mev (lab). Further analysis gives the p-p and p-n cross sections as 104 mb for the p-p reaction cross section and 113 mb for the p-n reaction cross section. The respective annihilation cross sections are 89 and 74 mb. The Glauber correction necessary in order to pass from the p-d to the p-n cross section by subtraction of the p-p cross section is unfortunately large and somewhat uncertain. The data are compared with the p-p and p-n cross sections and with other results on p-p collisions.

  19. Recent advances in modeling fission cross sections over intermediate...

    Office of Scientific and Technical Information (OSTI)

    Country of Publication: United States Language: English Subject: 73; APPROXIMATIONS; CROSS SECTIONS; DECAY AMPLITUDES; DEFORMATION; FISSION; FLUCTUATIONS; INTERMEDIATE STRUCTURE; ...

  20. Quantitative infrared absorption cross sections of isoprene for...

    Office of Scientific and Technical Information (OSTI)

    Quantitative infrared absorption cross sections of isoprene for atmospheric measurements ... and other oxygenated organics, yet little quantitative IR data exists for isoprene. ...

  1. Positive Scattering Cross Sections using Constrained Least Squares

    SciTech Connect (OSTI)

    Dahl, J.A.; Ganapol, B.D.; Morel, J.E.

    1999-09-27

    A method which creates a positive Legendre expansion from truncated Legendre cross section libraries is presented. The cross section moments of order two and greater are modified by a constrained least squares algorithm, subject to the constraints that the zeroth and first moments remain constant, and that the standard discrete ordinate scattering matrix is positive. A method using the maximum entropy representation of the cross section which reduces the error of these modified moments is also presented. These methods are implemented in PARTISN, and numerical results from a transport calculation using highly anisotropic scattering cross sections with the exponential discontinuous spatial scheme is presented.

  2. Calculation of nuclear reaction cross sections on excited nuclei...

    Office of Scientific and Technical Information (OSTI)

    Calculation of nuclear reaction cross sections on excited nuclei with the coupled-channels method Citation Details In-Document Search Title: Calculation of nuclear reaction cross ...

  3. Measurement of cross section of quark pair production top with...

    Office of Scientific and Technical Information (OSTI)

    Measurement of cross section of quark pair production top with the D0 experiment at the Tevatron and determination the top quark mass using this measure Citation Details ...

  4. Exclusive Neutrino Cross Sections From MiniBooNE

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

    Exclusive Neutrino Cross Sections From MiniBooNE Martin Tzanov University of Colorado PANIC 2008, 9-14 November, Eilat, ISRAEL Martin Tzanov, PANIC 2008 Neutrino Cross Sections Today * Precise knowledge needed for precise oscillation measurements. * Cross section well measured above 20 GeV. * Few measurements below 20 GeV. * 20-30 years old bubble chamber experiments (mostly H 2 , D 2 ). * Neutral current cross sections are even less understood. ν CC world data CC world data ν T2K, BooNE K2K,

  5. Neutron Induced Cross Sections for Radiochemistry for Isotopes of Arsenic

    SciTech Connect (OSTI)

    Kelley, K; Hoffman, R D; Dietrich, F S; Mustafa, M

    2006-01-10

    We have developed a set of modeled nuclear reaction cross sections for use in radiochemical diagnostics. Local systematics for the input parameters required by the Hauser-Feshbach statistical model were developed and used to calculate neutron induced nuclear reaction cross sections for isotopes of Arsenic (Z = 33) in the mass range 71 {le} A {le} 77.

  6. Scaling properties of proton-nucleus total reaction cross sections

    SciTech Connect (OSTI)

    Abu-Ibrahim, Badawy; Kohama, Akihisa

    2010-05-15

    We study the scaling properties of proton-nucleus total reaction cross sections for stable nuclei and propose an approximate expression in proportion to Z{sup 2/3}sigma{sub pp}{sup total}+N{sup 2/3}sigma{sub pn}{sup total}. Based on this expression, we can derive a relation that enables us to predict a total reaction cross section for any stable nucleus within 10% uncertainty at most, using the empirical value of the total reaction cross section of a given nucleus.

  7. Giant dipole resonance parameters with uncertainties from photonuclear cross sections

    SciTech Connect (OSTI)

    Plujko, V.A.; Capote, R.; Gorbachenko, O.M.

    2011-09-15

    Updated values and corresponding uncertainties of isovector giant dipole resonance (IVGDR or GDR) model parameters are presented that are obtained by the least-squares fitting of theoretical photoabsorption cross sections to experimental data. The theoretical photoabsorption cross section is taken as a sum of the components corresponding to excitation of the GDR and quasideuteron contribution to the experimental photoabsorption cross section. The present compilation covers experimental data as of January 2010. - Highlights: {yields} Experimental {sigma} ({gamma}, abs) or a sum of partial cross sections are taken as input to the fitting. {yields} Data include contributions from photoproton reactions. {yields} Standard (SLO) or modified (SMLO) Lorentzian approaches are used for formulating GDR models. {yields} Spherical or axially deformed nuclear shapes are used in GDR least-squares fit. {yields} Values and uncertainties of the SLO and SMLO GDR model parameters are tabulated.

  8. Measurement of cross section of quark pair production top with...

    Office of Scientific and Technical Information (OSTI)

    cross section of quark pair production top with the D0 experiment at the Tevatron and determination the top quark mass using this measure Citation Details In-Document Search Title: ...

  9. Measurement of the top quark pair production cross section in...

    Office of Scientific and Technical Information (OSTI)

    Measurement of the top quark pair production cross section in proton-proton collisions at sqrts13 TeV Citation Details In-Document Search Title: Measurement of the top quark...

  10. MiniBooNE QE Cross Section Data Release

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

    Current Quasielastic Double Differential Cross section", arXiv:1002:2680 hep-ex, Phys. Rev. D81, 092005 (2010) The following MiniBooNE information from the 2010 CCQE cross...

  11. Preliminary Geologic Map and Cross Sections of the Casa Diablo...

    Open Energy Info (EERE)

    and Cross Sections of the Casa Diablo Geothermal Area, Long Valley Caldera, Mono County, California Jump to: navigation, search OpenEI Reference LibraryAdd to library Map:...

  12. Nucleon-nucleon cross sections in nuclear matter

    SciTech Connect (OSTI)

    Schulze, H.; Schnell, A.; Roepke, G.; Lombardo, U.

    1997-06-01

    We provide a microscopic calculation of neutron-proton and neutron-neutron cross sections in symmetric nuclear matter at various densities, using the Brueckner-Hartree-Fock approximation scheme with the Paris potential. We investigate separately the medium effects on the effective mass and on the scattering amplitude. We determine average cross sections suitable for application in the dynamical simulation of heavy ion collisions, including a parametrization of their energy and density dependence. {copyright} {ital 1997} {ital The American Physical Society}

  13. Top Quark Pair Production Cross Section at the Tevatron

    SciTech Connect (OSTI)

    Peters, Reinhild Yvonne

    2015-09-25

    The top quark, discovered in 1995 by the CDF and D0 collaborations at the Tevatron proton antiproton collider at Fermilab, has undergone intense studies in the last 20 years. Currently, CDF and D0 converge on their measurements of top-antitop quark production cross sections using the full Tevatron data sample. In these proceedings, the latest results on inclusive and differential measurements of top-antitop quark production cross sections at the Tevatron are reported.

  14. A Multigroup Reaction Cross-Section Collapsing Code and Library of 154-Group Fission-Product Cross Sections.

    Energy Science and Technology Software Center (OSTI)

    1983-03-23

    Version 01/02 The code reads multigroup cross sections from a compatible data file and collapses user-selected reaction cross sections to any few-group structure using one of a variety of user neutron flux spectrum options given below: Option Flux description 1 Built-in function including Maxwellian, fission, fusion and slowing-down regions and requiring user-specified parameters and energy-region boundaries. 2 Set of log-log flux-energy interpolation points read from input cross-section data file. 3 Set of log-log flux-energy interpolationmore » points read from user-supplied card input. 4 - 6 Histogram flux values read from user-supplied card input in arbitrary group structure in units of flux-per unit-energy, flux-per-unit lethargy, or integral group flux. LAFPX-E may be used to collapse any set of multigroup reaction cross sections furnished in the required format. However, the code was developed for, and is furnished with, a library of 154-group fission-product cross sections processed from ENDF/B-IV with a typical light water reactor (LWR) flux spectrum and temperature. Four-group radiative capture cross sections produced for LWR calculations are tabulated in the code documentation and are incorporated in the EPRI-CINDER data library, RSIC Code Package CCC-309.« less

  15. ACTIV87: Fast Neutron Activation Cross Section File

    Energy Science and Technology Software Center (OSTI)

    1993-08-01

    4. HISTORICAL BACKGROUND AND INFORMATION ACTIV87 is a compilation of fast neutron induced activation reaction cross-sections. The compilation covers energies from threshold to 20 MeV and is based on evaluated data taken from other evaluated data libraries and individual evaluations. The majority of these evaluations were performed by using available experimental data. The aforementioned available experimental data were used in the selection of needed parameters for theoretical computations and for normalizing the results of suchmore » computations. Theoretical calculations were also used for interpolation and extrapolation of experimental cross-section data. All of the evaluated data curves were compared with experimental data that had been reported over the four year period preceding 1987. Only those cross-sections not in contradiction with experimental data that was current in 1987 were retained in the activation file, ACTIV87. In cases of several conflicting evaluations, that evaluation was chosen which best corresponded to the experimental data. A few evaluated curves were renormalized in accordance with the results of the latest precision measurements. 5. APPLICATION OF THE DATA 6. SOURCE AND SCOPE OF DATA The following libraries and individual files of evaluated neutron cross-section data were used for the selection of the activation cross-sections: the BOSPOR Library, the Activation File of the Evaluated Nuclear Data Library, the Evaluated Neutron Data File (ENDF/B-V) Activation File, the International Reactor Dosimetry File (IRDF-82), and individual evaluations carried out under various IAEA research contracts. The file of selected reactions contains 206 evaluated cross-section curves of the (n,2n), (n,p) and (n,a) reactions which lead to radioactive products and may be used in many practical applications of neutron activation analysis. Some competing activation reactions, usually with low cross-section values, are given for completeness.« less

  16. Experience With the SCALE Criticality Safety Cross Section Libraries

    SciTech Connect (OSTI)

    Bowman, S.M.

    2000-08-21

    This report provides detailed information on the SCALE criticality safety cross-section libraries. Areas covered include the origins of the libraries, the data on which they are based, how they were generated, past experience and validations, and performance comparisons with measured critical experiments and numerical benchmarks. The performance of the SCALE criticality safety cross-section libraries on various types of fissile systems are examined in detail. Most of the performance areas are demonstrated by examining the performance of the libraries vs critical experiments to show general trends and weaknesses. In areas where directly applicable critical experiments do not exist, performance is examined based on the general knowledge of the strengths and weaknesses of the cross sections. In this case, the experience in the use of the cross sections and comparisons with the results of other libraries on the same systems are relied on for establishing acceptability of application of a particular SCALE library to a particular fissile system. This report should aid in establishing when a SCALE cross-section library would be expected to perform acceptably and where there are known or suspected deficiencies that would cause the calculations to be less reliable. To determine the acceptability of a library for a particular application, the calculational bias of the library should be established by directly applicable critical experiments.

  17. Cross-Sectional Transport Imaging in a Multijunction Solar Cell

    SciTech Connect (OSTI)

    Haegel, Nancy M.; Ke, Chi-Wen; Taha, Hesham; Guthrey, Harvey; Fetzer, C. M.; King, Richard

    2015-06-14

    Combining highly localized electron-beam excitation at a point with the spatial resolution capability of optical near-field imaging, we have imaged carrier transport in a cross-sectioned multijunction (GaInP/GaInAs/Ge) solar cell. We image energy transport associated with carrier diffusion throughout the full width of the middle (GaInAs) cell and luminescent coupling from point excitation in the top cell GaInP to the middle cell. Supporting cathodoluminescence and near-field photoluminescence measurements demonstrate excitation-dependent Fermi level splitting effects that influence cross-sectioned spectroscopy results as well as transport limitations on the spatial resolution of cross-sectional measurements.

  18. Dosimetry and cross section measurements at RTNS II

    SciTech Connect (OSTI)

    Greenwood, L.R.; Kneff, D.W.

    1987-01-01

    Numerous measurements have been conducted at TRNS-II in order to map the neutron field for materials irradiations, to measure activation cross sections, and to measure helium production cross sections. Experiments of up to two weeks duration irradiated large numbers of activation dosimetry and helium samples both close to the source and throughout the target room. Many other samples have been irradiated in piggy-back positions over periods lasting many months. All of these experiments fall into four main classes, namely, fluence-mapping, activation dosimetry, the production of long-lived isotopes, and helium generation measurements. Radiometric dosimetry and activation cross section measurements were performed at Argonne National Laboratory; helium production was measured at Rockwell International Corporation. This paper briefly summarizes the principal results of our measurements at RTNS-II; references are given for more detailed publications. 14 refs., 4 figs.

  19. Uncertainty quantification in fission cross section measurements at LANSCE

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

    Tovesson, F.

    2015-01-09

    Neutron-induced fission cross sections have been measured for several isotopes of uranium and plutonium at the Los Alamos Neutron Science Center (LANSCE) over a wide range of incident neutron energies. The total uncertainties in these measurements are in the range 3–5% above 100 keV of incident neutron energy, which results from uncertainties in the target, neutron source, and detector system. The individual sources of uncertainties are assumed to be uncorrelated, however correlation in the cross section across neutron energy bins are considered. The quantification of the uncertainty contributions will be described here.

  20. Neutron capture cross section standards for BNL 325, Fourth Edition

    SciTech Connect (OSTI)

    Holden, N.E.

    1981-01-01

    This report evaluates the experimental data and recommends values for the thermal neutron cross sections and resonance integrals for the neutron capture reactions: /sup 55/Mn(n,..gamma..), /sup 59/Co(n,..gamma..) and /sup 197/Au(n,..gamma..). The failure of lithium and boron as standards due to the natural variation of the absorption cross sections of these elements is discussed. The Westcott convention, which describes the neutron spectrum as a thermal Maxwellian distribution with an epithermal component, is also discussed.

  1. C+C Fusion Cross Sections Measurements for Nuclear Astrophysics

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

    Almaraz-Calderon, S.; Carnelli, P. F. F.; Rehm, K. E.; Albers, M.; Alcorta, M.; Bertone, P. F.; Digiovine, B.; Esbensen, H.; Fernandez Niello, J. O.; Henderson, D.; et al

    2015-06-02

    Total fusion cross section of carbon isotopes were obtained using the newly developed MUSIC detector. MUSIC is a highly efficient, active target-detector system designed to measure fusion excitation functions with radioactive beams. The present measurements are relevant for understanding x-ray superbursts. The results of the first MUSIC campaign as well as the astrophysical implications are presented in this work.

  2. RZ calculations for self shielded multigroup cross sections

    SciTech Connect (OSTI)

    Li, M.; Sanchez, R.; Zmijarevic, I.; Stankovski, Z.

    2006-07-01

    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)

  3. Reaction cross sections of carbon isotopes incident on a proton

    SciTech Connect (OSTI)

    Abu-Ibrahim, B.; Horiuchi, W.; Kohama, A.; Suzuki, Y.

    2008-03-15

    We systematically study total reaction cross sections of carbon isotopes with N=6-16 on a proton target for wide range of incident energies. An emphasis is put on the difference from the case of a carbon target. The calculations include the reaction cross sections of {sup 19,20,22}C at 40A MeV, the data of which have recently been measured at RIKEN. The Glauber theory is used to calculate the reaction cross sections. To describe the intrinsic structure of the carbon isotopes, we use a Slater determinant generated from a phenomenological mean-field potential, and construct the density distributions. To go beyond the simple mean-field model, we adopt two types of dynamical models: One is a core+n model for odd-neutron nuclei, and the other is a core+n+n model for {sup 16}C and {sup 22}C. We propose empirical formulas which are useful in predicting unknown cross sections.

  4. 70 Group Neutron Fast Reactor Cross Section Set and 25 Group Neutron Fast Reactor Cross Section Set.

    Energy Science and Technology Software Center (OSTI)

    1984-10-29

    Version 00 These multigroup cross sections are used in fast reactor calculations. The benchmark calculations for the 23 fast critical assemblies used in the benchmark tests of JFS-2 were performed with one-dimensional diffusion theory by using the JFS-3-J2 set.

  5. Vortex breakdown in closed containers with polygonal cross sections

    SciTech Connect (OSTI)

    Naumov, I. V. Dvoynishnikov, S. V.; Kabardin, I. K.; Tsoy, M. A.

    2015-12-15

    The vortex breakdown bubble in the confined flow generated by a rotating lid in closed containers with polygonal cross sections was analysed both experimentally and numerically for the height/radius aspect ratio equal to 2. The stagnation point locations of the breakdown bubble emergence and the corresponding Reynolds number were determined experimentally and in addition computed numerically by STAR-CCM+ CFD software for square, pentagonal, hexagonal, and octagonal cross section configurations. The flow pattern and the velocity were observed and measured by combining the seeding particle visualization and the temporal accuracy of laser Doppler anemometry. The vortex breakdown size and position on the container axis were determined for Reynolds numbers, ranging from 1450 to 2400. The obtained results were compared with the flow structure in the closed container of cubical and cylindrical configurations. It is shown that the measured evolution of steady vortex breakdown is in close agreement with the numerical results.

  6. Accurate Development of Thermal Neutron Scattering Cross Section Libraries

    SciTech Connect (OSTI)

    Hawari, Ayman; Dunn, Michael

    2014-06-10

    The objective of this project is to develop a holistic (fundamental and accurate) approach for generating thermal neutron scattering cross section libraries for a collection of important enutron moderators and reflectors. The primary components of this approach are the physcial accuracy and completeness of the generated data libraries. Consequently, for the first time, thermal neutron scattering cross section data libraries will be generated that are based on accurate theoretical models, that are carefully benchmarked against experimental and computational data, and that contain complete covariance information that can be used in propagating the data uncertainties through the various components of the nuclear design and execution process. To achieve this objective, computational and experimental investigations will be performed on a carefully selected subset of materials that play a key role in all stages of the nuclear fuel cycle.

  7. Inclusive jet cross-section measurement at CDF

    SciTech Connect (OSTI)

    Norniella, Olga; /Barcelona, IFAE

    2007-05-01

    The CDF Collaboration has measured the inclusive jet cross section using 1992-93 collider data at 1.8 TeV. The CDF measurement is in very good agreement with NLO QCD predictions for transverse energies (E{sub T}) below 200 GeV. However, it is systematically higher than NLO QCD predictions for E{sub T} above 200 GeV.

  8. Top Quark Production Cross Section at the Tevatron

    SciTech Connect (OSTI)

    Shabalina, E.; /Chicago U.

    2006-05-01

    An overview of the preliminary results of the top quark pair production cross section measurements at a center-of-mass energy of 1.96 TeV carried out by the CDF and D0 collaborations is presented. The data samples used for the analyses are collected in the current Tevatron run and correspond to an integrated luminosity from 360 pb{sup -1} up to 760 pb{sup -1}.

  9. Radial Eigenmodes for a Toroidal Waveguide with Rectangular Cross Section

    SciTech Connect (OSTI)

    Rui Li

    2012-07-01

    In applying mode expansion to solve the CSR impedance for a section of toroidal vacuum chamber with rectangular cross section, we identify the eigenvalue problem for the radial eigenmodes which is different from that for cylindrical structures. In this paper, we present the general expressions of the radial eigenmodes, and discuss the properties of the eigenvalues on the basis of the Sturm-Liouville theory.

  10. Laser stimulated emission cross sections of Nd glasses

    SciTech Connect (OSTI)

    Tucker, A.W.; Birnbaum, M.; Fincher, C.L.

    1982-01-01

    A laser-comparison method was used to determine the emission cross sections at 1060 nm of Nd glasses used in laser fusion systems. The values obtained for two phosphate glasses (LHG-8) and (Q-88) were 4.0 +- 0.8 x 10/sup -20/ cm/sup 2/ and 1.7 +- 0.5 x 10/sup -20/ cm/sup 2/ for a silicate glass (LG-650).

  11. Neutron Cross-Section Measurements on Structural Materials at ORELA

    SciTech Connect (OSTI)

    Guber, Klaus H; Koehler, Paul; Wiarda, Dorothea; Harvey, John A

    2011-01-01

    Neutron capture experiments, using isotopically enriched and natural samples of chromium and titanium, were performed on flight paths 6 and 7 at the 40 m flight station of ORELA. The experimental data were acquired using a pair of deuterated benzene detectors employing the now well-established pulse-height-weighting technique. These data were complemented by new total cross-section measurements where no useful previous data were available.

  12. Top quark pair production cross section at the Tevatron

    SciTech Connect (OSTI)

    Cortiana, Giorgio; /INFN, Padua /Padua U.

    2008-04-01

    Top quark pair production cross section has been measured at the Tevatron by CDF and D0 collaborations using different channels and methods, in order to test standard model predictions, and to search for new physics hints affecting the t{bar t} production mechanism or decay. Measurements are carried out with an integrated luminosity of 1.0 to 2.0 fb{sup -1}, and are found to be consistent with standard model expectations.

  13. Nuclear Astrophysics and Neutron Cross Section Measurements Using the ORELA

    SciTech Connect (OSTI)

    Winters, R. R.

    2000-08-25

    This is the final report for a research program which has been continuously supported by the AEC, ERDA, or USDOE since 1973. The neutron total and capture cross sections for n + {sup 88}Sr have been measured over the neutron energy range 100 eV to 1 MeV. The report briefly summaries our results and the importance of this work for nucleosynthesis and the optical model.

  14. Overview of recent U235 neutron cross section evaluation work

    SciTech Connect (OSTI)

    Lubitz, C. [Lockheed Martin Corp., Schenectady, NY (United States)

    1998-10-01

    This report is an overview (through 1997) of the U235 neutron cross section evaluation work at Oak Ridge National Laboratory (ORNL), AEA Technology (Harwell) and Lockheed Martin Corp.-Schenectady (LMS), which has influenced, or appeared in, ENDF/B-VI through Release 5. The discussion is restricted to the thermal and resolved resonance regions, apart from some questions about the unresolved region which still need investigation. The important role which benchmark testing has played will be touched on.

  15. Deuterium target data for precision neutrino-nucleus cross sections

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

    Meyer, Aaron S.; Betancourt, Minerba; Gran, Richard; Hill, Richard J.

    2016-06-23

    Amplitudes derived from scattering data on elementary targets are basic inputs to neutrino-nucleus cross section predictions. A prominent example is the isovector axial nucleon form factor, FA(q2), which controls charged current signal processes at accelerator-based neutrino oscillation experiments. Previous extractions of FA from neutrino-deuteron scattering data rely on a dipole shape assumption that introduces an unquantified error. A new analysis of world data for neutrino-deuteron scattering is performed using a model-independent, and systematically improvable, representation of FA. A complete error budget for the nucleon isovector axial radius leads to rA2 = 0.46(22)fm2, with a much larger uncertainty than determined inmore » the original analyses. The quasielastic neutrino-neutron cross section is determined as σ(νμn → μ-p)|Ev=1GeV = 10.1(0.9)×10-39cm2. The propagation of nucleon-level constraints and uncertainties to nuclear cross sections is illustrated using MINERvA data and the GENIE event generator. Furthermore, these techniques can be readily extended to other amplitudes and processes.« less

  16. Positive anisotropic group scattering cross sections for radiation transport

    SciTech Connect (OSTI)

    DelGrande, J.M.

    1999-05-01

    In solving the Boltzmann transport equation, most discrete ordinates codes calculate the source term by first approximating the scattering cross section using a Legendre polynomial expansion. Such expansions are insufficient when scattering is anisotropic and the Legendre expansion is truncated prematurely. This can lead to nonphysical negative cross sections, negative source terms and negative angular fluxes. While negative sources are problematic for standard discrete ordinates methods leading to poor convergence or convergence to incorrect results, they are of particular concern to exponential methods, causing such calculations to fail. The authors` have developed and tested a new technique to solve this problem called the Monte Carlo Facet Method. This method is an extension of standard Monte Carlo techniques. It guarantees non-negative cross sections at all directional ordinates. It also ensures within group and next group scatter. This dissertation outlines previous attempts to handle anisotropic scattering to achieve non-negative sources. It develops the theory of the Monte Carlo facet method and its first angular moment conservation. Results are presented examining the scattering matrices for various materials, and finally demonstrating that these scattering matrices perform exceptionally well in a multi-group, anisotropic, unstructured mesh discrete ordinates transport code.

  17. Neutron Capture Cross Sections for the Re/Os Clock

    SciTech Connect (OSTI)

    Mosconi, M.; Heil, M.; Kaeppeler, F.; Plag, R.; Voss, F.; Wisshak, K.; Mengoni, A.; Cennini, P.; Chiaveri, E.; Ferrari, A.; Fitzpatrick, L.; Herrera-Martinez, A.; Kadi, Y.; Sarchiapone, L.; Vlachoudis, V.; Wendler, H.; Aerts, G.; Andriamonje, S.; Berthoumieux, E.; Dridi, W.

    2005-05-24

    The radioactive decay of 187Re {yields} 187Os (t1/2 = 43 Gyr) is suited for dating the onset of heavy-element nucleosynthesis. The radiogenic contribution to the 187Os abundance is the difference between the natural abundance and the corresponding s-process component. This component can be obtained via the well-established {sigma}N systematics using the neighboring s-only isotope 186Os, provided the neutron-capture cross sections of both isotopes are known with sufficient accuracy. We report on a new set of experiments performed with a C6D6 detector array at the n{sub T}OF neutron spallation facility of CERN. The capture cross sections of 186Os, 187Os, and 188Os have been measured in the neutron-energy range between 1 eV and 1 MeV, and Maxwellian-averaged cross sections were deduced for the relevant thermal energies from kT=5 keV to 100 keV.

  18. From ZZ to ZH : How Low Can These Cross Sections Go or Everybody, Let's Cross Section Limbo!

    SciTech Connect (OSTI)

    Strauss, Emanuel Alexandre; /SUNY, Stony Brook

    2009-08-01

    We report on two searches performed at the D0 detector at the Fermi National Laboratory. The first is a search for Z di-boson production with a theoretical cross section of 1.4 pb. The search was performed on 2.6 fb{sup -1} of data and contributed to the first observation of ZZ production at a hadron collider. The second is a search for a low mass Standard Model Higgs in 4.2 fb{sup -1} of data. The Higgs boson is produced in association with a Z boson where the Higgs decays hadronically and the Z decays to two leptons. The ZZ search was performed in both the di-electron and di-muon channels. For the ZH search, we will focus on the muonic decays where we expanded the traditional coverage by considering events in which one of the two muons fails the selection requirement, and is instead reconstructed as an isolated track. We consider Higgs masses between 100 and 150 GeV, with theoretical cross sections ranging from 0.17 to 0.042 pb, and set upper limits on the ZH production cross-section at 95% confidence level.

  19. Radioactive targets for neutron-induced cross section measurements

    SciTech Connect (OSTI)

    Kronenberg, A.; Bond, E. M.; Glover, S. E.; Rundberg, R. S.; Vieira, D. J.; Esch, E. I.; Reifarth, R.; Ullmann, J. L.; Haight, Robert C.; Rochmann, D.

    2004-01-01

    Measurements using radioactive targets are important for the determination of key reaction path ways associated with the synthesis of the elements in nuclear astrophysics (sprocess), advanced fuel cycle initiative (transmutation of radioactive waste), and stockpile stewardship. High precision capture cross-section measurements are needed to interpret observations, predict elemental or isotopical ratios, and unobserved abundances. There are two new detector systems that are presently being commissioned at Los Alamos National Laboratory for very precise measurements of (n,{gamma}) and (n,f) cross-sections using small quantities of radioactive samples. DANCE (Detector for Advanced Neutron-Capture Experiments), a 4 {pi} gamma array made up of 160 BaF{sub 2} detectors, is designed to measure neutron capture cross-sections of unstable nuclei in the low-energy range (thermal to {approx}500 keV). The high granularity and high detection efficiency of DANCE, combined with the high TOF-neutron flux available at the Lujan Center provides a versatile tool for measuring many important cross section data using radioactive and isotopically enriched targets of about 1 milligram. Another powerful instrument is the Lead-slowing down spectrometer (LSDS), which will enable the measurement of neutron-induced fission cross-section of U-235m and other short-lived actinides in a energy range from 1-200 keV with sample sizes down to 10 nanograms. Due to the short half-life of the U-235m isomer (T{sub 1/2} = 26 minutes), the samples must be rapidly and repeatedly extracted from its {sup 239}Pu parent. Since {sup 239}Pu is itself highly fissile, the separation must not only be rapid, but must also be of very high purity (the Pu must be removed from the U with a decontamination factor >10{sup 12}). Once extracted and purified, the {sup 235m}U isomer would be electrodeposited on solar cells as a fission detector and placed within the LSDS for direct (n,f) cross section measurements. The

  20. Detailed photonuclear cross-section calculations and astrophysical applications

    SciTech Connect (OSTI)

    Gardner, D.G.; Gardner, M.A.; Hoff, R.W.

    1989-06-15

    We have investigated the role of an isomeric state and its coupling to the ground state (g.s.) via photons and neutron inelastic scattering in a stellar environment by making detailed photonuclear and neutron cross-section calculations for /sup 176/Lu and /sup 210/Bi. In the case of /sup 176/Lu, the g.s. would function as an excellent galactic slow- (s-) process chronometer were it not for the 3.7-h isomer at 123 keV. Our calculations predicted much larger photon cross sections for production of the isomer, as well as a lower threshold, than had been assumed based on earlier measurements. These two factors combine to indicate that an enormous correction, a factor of 10/sup 7/, must be applied to shorten the current estimate of the half-life against photoexcitation of /sup 176/Lu as a function of temperature. This severely limits the use of /sup 176/Lu as a stellar chronometer and indicates a significantly lower temperature at which the two states reach thermal equilibrium. For /sup 210/Bi, our preliminary calculations of the production and destruction of the 3 /times/ 10/sup 6/ y isomeric state by neutrons and photons suggest that the /sup 210/Bi isomer may not be destroyed by photons as rapidly as assumed in certain stellar environments. This leads to an alternate production path of /sup 207/Pb and significantly affects presently interpreted lead isotopic abundances. We have been able to make such detailed nuclear cross-section calculations using: modern statistical-model codes of the Hauser-Feshbach type, with complete conservation of angular momentum and parity; reliable systematics of the input parameters required by these codes, including knowledge of the absolute gamma-ray strength-functions for E1, M1, and E2 transitions; and codes developed to compute large, discrete, nuclear level sets, their associated gamma-ray branchings, and the presence and location of isomeric states. 7 refs., 2 figs.

  1. MOX Cross-Section Libraries for ORIGEN-ARP

    SciTech Connect (OSTI)

    Gauld, I.C.

    2003-07-01

    The use of mixed-oxide (MOX) fuel in commercial nuclear power reactors operated in Europe has expanded rapidly over the past decade. The predicted characteristics of MOX fuel such as the nuclide inventories, thermal power from decay heat, and radiation sources are required for design and safety evaluations, and can provide valuable information for non-destructive safeguards verification activities. This report describes the development of computational methods and cross-section libraries suitable for the analysis of irradiated MOX fuel with the widely-used and recognized ORIGEN-ARP isotope generation and depletion code of the SCALE (Standardized Computer Analyses for Licensing Evaluation) code system. The MOX libraries are designed to be used with the Automatic Rapid Processing (ARP) module of SCALE that interpolates appropriate values of the cross sections from a database of parameterized cross-section libraries to create a problem-dependent library for the burnup analysis. The methods in ORIGEN-ARP, originally designed for uranium-based fuels only, have been significantly upgraded to handle the larger number of interpolation parameters associated with MOX fuels. The new methods have been incorporated in a new version of the ARP code that can generate libraries for low-enriched uranium (LEU) and MOX fuel types. The MOX data libraries and interpolation algorithms in ORIGEN-ARP have been verified using a database of declared isotopic concentrations for 1042 European MOX fuel assemblies. The methods and data are validated using a numerical MOX fuel benchmark established by the Organization for Economic Cooperation and Development (OECD) Working Group on burnup credit and nuclide assay measurements for irradiated MOX fuel performed as part of the Belgonucleaire ARIANE International Program.

  2. Comprehensive Nuclear Model Code, Nucleons, Ions, Induced Cross-Sections

    Energy Science and Technology Software Center (OSTI)

    2002-09-27

    EMPIRE-II is a flexible code for calculation of nuclear reactions in the frame of combined op0tical, Multistep Direct (TUL), Multistep Compound (NVWY) and statistical (Hauser-Feshbach) models. Incident particle can be a nucleon or any nucleus (Heavy Ion). Isomer ratios, residue production cross sections and emission spectra for neutrons, protons, alpha- particles, gamma-rays, and one type of Light Ion can be calculated. The energy range starts just above the resonance region for neutron induced reactions andmore » extends up to several hundreds of MeV for the Heavy Ion induced reactions.« less

  3. Proton radiography, nuclear cross sections and multiple Coulomb scattering

    SciTech Connect (OSTI)

    Sjue, Sky K.

    2015-11-04

    The principles behind proton radiography including multiple Coulomb scattering are discussed for a purely imaginary square well nucleus in the eikonal approximation. It is found that a very crude model can reproduce the angular dependence of the cross sections measured at 24 GeV/c. The largest differences are ~3% for the 4.56 mrad data, and ~4% for the 6.68 mrad data. The prospect of understanding how to model deterministically high-energy proton radiography over a very large range of energies is promising, but it should be tested more thoroughly.

  4. Final Report - Nucelar Astrophysics & Neutron Cross Section Measurements

    SciTech Connect (OSTI)

    Carlton, Robert F

    2009-12-01

    This enduring research program of 28 years has taken advantage of the excellent research facility of ORELA at Oak Ridge National Laboratory. The fruitful collaborations include a number of scientists from ORNL and some from LASL. This program which has ranged from nuclear structure determinations to astrophysical applications has resulted in the identification and/or the refinement of the nuclear properties of more than 5,000 nuclear energy levels or compound energy states. The nuclei range from 30Si to 250Cf, the probes range from thermal to 50 MeV neutrons, and the studies range from capture gamma ray spectra to total and differential scattering and absorption cross sections. Specific target nuclei studied include the following: 120Sn 124Sn 125Sn 113Sn 115Sn 117Sn 119Sn 249Cf 33S 34S 249Bk 186Os 187Os 188Os 30Si 32S 40Ca 48Ca 60Ni 54Fe 86Kr 88Sr 40Ar 122Sn 90Zr 122Sn(n,?) 208Pb 204Pb 52Cr 54Cr 50Cr 53Cr As can be seen, we have studied, on average, more than one isotope per year of grant funding and have focused on exploiting those elements having multiple isotopes in order to investigate systematic trends in nuclear properties, for the purpose of providing more stringent tests of the nuclear spherical optical model with a surface imaginary potential. We have investigated an l-dependence of the real-well depth of the spherical optical model; we have used these measurements to deduce the existence of doorway states in the compound nucleus; and in the total cross section measurements we have, in addition to resonance energies and widths, obtained values for the level density and neutron strength function. Due to the high neutron energy resolution of the ORELA and in some cases the addition of differential scattering cross section data, we have been able to disaggregate the spin states and provide level spacing and strength function for each partial wave in the neutron-nucleus interaction, in some cases up to d5/2. In the following we will summarize the most recent

  5. Comprehensive Nuclear Model Code, Nucleons, Ions, Induced Cross-Sections

    Energy Science and Technology Software Center (OSTI)

    2002-09-27

    EMPIRE-II is a flexible code for calculation of nuclear reactions in the frame of combined op0tical, Multistep Direct (TUL), Multistep Compound (NVWY) and statistical (Hauser-Feshbach) models. Incident particle can be a nucleon or any nucleus (Heavy Ion). Isomer ratios, residue production cross sections and emission spectra for neutrons, protons, alpha- particles, gamma-rays, and one type of Light Ion can be calculated. The energy range starts just above the resonance region for neutron induced reactions andmore »extends up to several hundreds of MeV for the Heavy Ion induced reactions.« less

  6. Regularization scheme independence and unitarity in QCD cross sections

    SciTech Connect (OSTI)

    Catani, S.; Seymour, M.H.; Trocsanyi, Z.

    1997-06-01

    When calculating next-to-leading order QCD cross sections, divergences in intermediate steps of the calculation must be regularized. The final result is independent of the regularization scheme used, provided that it is unitary. In this paper we explore the relationship between regularization scheme independence and unitarity. We show how the regularization scheme dependence can be isolated in simple universal components, and how unitarity can be guaranteed for any regularization prescription that can consistently be introduced in one-loop amplitudes. Finally, we show how to derive transition rules between different schemes without having to do any loop calculations. {copyright} {ital 1997} {ital The American Physical Society}

  7. CROSS SECTION EVALUATIONS FOR ENDF/B-VII.

    SciTech Connect (OSTI)

    HERMAN, M.; ROCHMAN, D.; OBLOZINSKY, P.

    2006-06-05

    This is the final report of the work performed under the LANL contract on neutron cross section evaluations for ENDF/B-VII (April 2005-May 2006). The purpose of the contract was to ensure seamless integration of the LANL neutron cross section evaluations in the new ENDF/B-VII library. The following work was performed: (1) LANL evaluated data files submitted for inclusion in ENDF/B-VII were checked and, when necessary, formal formatting errors were corrected. As a consequence, ENDF checking codes, run on all LANL files, do not report any errors that would rise concern. (2) LANL dosimetry evaluations for {sup 191}Ir and {sup 193}Ir were completed to match ENDF requirements for the general purpose library suitable for transport calculations. A set of covariances for both isotopes is included in the ENDF files. (3) Library of fission products was assembled and successfully tested with ENDF checking codes, processed with NJOY-99.125 and simple MCNP calculations. (4) KALMAN code has been integrated with the EMPIRE system to allow estimation of covariances based on the combination of measurements and model calculations. Covariances were produced for 155,157-Gd and also for 6 remaining isotopes of Gd.

  8. Effect of strongly coupled plasma on photoionization cross section

    SciTech Connect (OSTI)

    Das, Madhusmita

    2014-01-15

    The effect of strongly coupled plasma on the ground state photoionization cross section is studied. In the non relativistic dipole approximation, cross section is evaluated from bound-free transition matrix element. The bound and free state wave functions are obtained by solving the radial Schrodinger equation with appropriate plasma potential. We have used ion sphere potential (ISP) to incorporate the plasma effects in atomic structure calculation. This potential includes the effect of static plasma screening on nuclear charge as well as the effect of confinement due to the neighbouring ions. With ISP, the radial equation is solved using Shooting method approach for hydrogen like ions (Li{sup +2}, C{sup +5}, Al{sup +12}) and lithium like ions (C{sup +3}, O{sup +5}). The effect of strong screening and confinement is manifested as confinement resonances near the ionization threshold for both kinds of ions. The confinement resonances are very much dependent on the edge of the confining potential and die out as the plasma density is increased. Plasma effect also results in appearance of Cooper minimum in lithium like ions, which was not present in case of free lithium like ions. With increasing density the position of Cooper minimum shifts towards higher photoelectron energy. The same behaviour is also true for weakly coupled plasma where plasma effect is modelled by Debye-Huckel potential.

  9. Status of the International Neutron Cross-Section Standards File

    SciTech Connect (OSTI)

    Pronyaev, Vladimir G.; Badikov, Sergei A.; Gai, Evgeny V.; Chen Zhenpeng; Carlson, Allan D.; Hale, Gerald M.; Hambsch, Franz-Josef; Hofmann, Hartmut M.; Larson, Nancy M.; Smith, Donald L.; Oh, Soo-Youl; Tagesen, Siegfried; Vonach, Herbert

    2005-05-24

    A report is given of the progress achieved in an IAEA Co-ordinated Research Project (CRP) to improve the cross-section standards. The objectives of the CRP, started in 2002, were initially the understanding of the origin of the strong uncertainty reduction in R-matrix model fits and the improvement of the evaluation methodology. These aims were extended in 2003 to the preparation of new evaluations for the standard 6Li(n,t), 10B(n,{alpha}), 10B(n,{alpha}1), 197Au(n,{gamma}), 235U(n,f), and 238U(n,f) reactions. The methodology, codes, and experimental database developed by Poenitz and Hale for the ENDF/B-VI standards evaluation were taken as the basis for the new evaluation. The major results achieved by the CRP participants include the testing and intercomparison of a number of codes that can be used in the standards evaluation, updating the database of experimental results, analysis of the reasons leading to the strong uncertainty reduction in model fits, and a study of the bias in evaluated data caused by the Peelles's Pertinent Puzzle (PPP) effect, which has been widely discussed in the nuclear data community since the ENDF/B-VI standards evaluation was completed. Preliminary results of the new standards evaluation are shown. The use of the new 235U(n,f) cross section leads to better consistency in calculations of some important integral experiments.

  10. Research on Fast-Doppler-Broadening of neutron cross sections

    SciTech Connect (OSTI)

    Li, S.; Wang, K.; Yu, G.

    2012-07-01

    A Fast-Doppler-Broadening method is developed in this work to broaden Continuous Energy neutron cross-sections for Monte Carlo calculations. Gauss integration algorithm and parallel computing are implemented in this method, which is unprecedented in the history of cross section processing. Compared to the traditional code (NJOY, SIGMA1, etc.), the new Fast-Doppler-Broadening method shows a remarkable speedup with keeping accuracy. The purpose of using Gauss integration is to avoid complex derivation of traditional broadening formula and heavy load of computing complementary error function that slows down the Doppler broadening process. The OpenMP environment is utilized in parallel computing which can take full advantage of modern multi-processor computers. Combination of the two can reduce processing time of main actinides (such as {sup 238}U, {sup 235}U) to an order of magnitude of 1{approx}2 seconds. This new method is fast enough to be applied to Online Doppler broadening. It can be combined or coupled with Monte Carlo transport code to solve temperature dependent problems and neutronics-thermal hydraulics coupled scheme which is a big challenge for the conventional NJOY-MCNP system. Examples are shown to determine the efficiency and relative errors compared with the NJOY results. A Godiva Benchmark is also used in order to test the ACE libraries produced by the new method. (authors)

  11. Neutron cross section standards and instrumentation. Annual report

    SciTech Connect (OSTI)

    Wasson, O.A.

    1993-07-01

    The objective of this interagency program is to provide accurate neutron interaction measurements for the US Department of Energy nuclear programs which include waste disposal, fusion, safeguards, defense, fission, and personnel protection. These measurements are also useful to other energy programs which indirectly use the unique properties of the neutron for diagnostic and analytical purposes. The work includes the measurement of reference cross sections and related neutron data employing unique facilities and capabilities at NIST and other laboratories as required; leadership and participation in international intercomparisons and collaborations; the preservation of standard reference deposits and the development of improved neutron detectors and measurement methods. A related and essential element of the program is critical evaluation of neutron interaction data including international coordinations. Data testing of critical data for important applications is included. The program is jointly supported by the Department of Energy and the National Institute of Standards and Technology. This report from the National Institute of Standards and Technology contains a summary of the accomplishments of the Neutron Cross Section Standards and Instrumentation Project during the third year of this three-year interagency agreement. The proposed program and required budget for the following three years are also presented. The program continues the shifts in priority instituted in order to broaden the program base.

  12. Deeply virtual Compton Scattering cross section measured with CLAS

    SciTech Connect (OSTI)

    Guegan, Baptistse

    2014-09-01

    The Generalized Parton Distributions (GPDs) provide a new description of nucleon structure in terms of its elementary constituents, the quarks and the gluons. Including and extending the information provided by the form factors and the parton distribution functions, they describe the correlation between the transverse position and the longitudinal momentum fraction of the partons in the nucleon. Deeply Virtual Compton Scattering (DVCS), the electroproduction of a real photon on a single quark in the nucleon eN --> e'N'g, is the exclusive process most directly interpretable in terms of GPDs. A dedicated experiment to study DVCS with the CLAS detector at Jefferson Lab has been carried out using a 5.9-GeV polarized electron beam and an unpolarized hydrogen target, allowing us to collect DVCS events in the widest kinematic range ever explored in the valence region : 1.0 < Q2 < 4.6 GeV2, 0.1 < xB < 0.58 and 0.09 < -t < 2.0 GeV2. In this paper, we show preliminary results of unpolarized cross sections and of polarized cross section differences for the DVCS channel.

  13. 102Pd(n, {gamma}) Cross Section Measurement Using DANCE

    SciTech Connect (OSTI)

    Hatarik, R.; Alpizar-Vicente, A. M. [Colorado School of Mines, Golden, CO 80401 (United States); Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); Bredeweg, T. A.; Esch, E.-I.; Haight, R. C.; O'Donnell, J. M.; Reifarth, R.; Rundberg, R. S.; Ullmann, J. L.; Vieira, D. J.; Wouters, J. M. [Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); Greife, U. [Colorado School of Mines, Golden, CO 80401 (United States)

    2006-03-13

    The neutron capture cross section of the proton rich nucleus 102Pd was measured with the Detector for Advanced Neutron Capture Experiments (DANCE) at the Los Alamos Neutron Science Center. The target was a 2 mg Pd foil with 78% enriched 102Pd. It was held by a 0.9 {mu}m thick Mylar bag which was selected after comparing different thicknesses of Kapton and Mylar for their scattering background. To identify the contribution of the other Pd isotopes the data of a natural Pd sample was compared to the data of the 102Pd enriched sample. A 12C sample was used to determine the scattering background. The 102Pd(n, {gamma}) rate is of importance for the p-process nucleosynthesis.

  14. SCWR Once-Through Calculations for Transmutation and Cross Sections

    SciTech Connect (OSTI)

    ganda, francesco

    2012-07-01

    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

  15. Validation of a large activation cross-section library

    SciTech Connect (OSTI)

    Muir, D.W.; Wilson, W.B.

    1994-06-01

    The 63-group neutron cross-section library used for neutron activation studies in the Nuclear Theory and Applications Group at Los Alamos has a variety of sources of widely varying levels of quality. This heterogeneous aspect, which is a common feature of all libraries used in activation studies, is a direct consequence of the need to quickly obtain data for up to 15,000 different excitation functions involving 750 different targets. Because of the need to assess the reliability of this library and ten to improve it, we have initiated a systematic comparison of this library with three main data sources, especially the large CSISRS online data system, maintained by the National Nuclear Data Center at Brookhaven National Laboratory. We report on the results of extensive comparisons between the experimental data and the multigroup library. We briefly mention new theoretical approaches data evaluation that are suitable for meeting future data needs in this area.

  16. Measurements of t anti-t production cross-section with D0 experiment...

    Office of Scientific and Technical Information (OSTI)

    Measurements of t anti-t production cross-section with D0 experiment Citation Details In-Document Search Title: Measurements of t anti-t production cross-section with D0 experiment ...

  17. Soda Lake Well Lithology Data and Geologic Cross-Sections (Dataset...

    Office of Scientific and Technical Information (OSTI)

    Soda Lake Well Lithology Data and Geologic Cross-Sections Title: Soda Lake Well Lithology Data and Geologic Cross-Sections Comprehensive catalogue of drill-hole data in ...

  18. Partial gamma-ray cross section measurements in 109Ag(n, x n...

    Office of Scientific and Technical Information (OSTI)

    Technical Report: Partial gamma-ray cross section measurements in 109Ag(n, x n y p gamma) reactions Citation Details In-Document Search Title: Partial gamma-ray cross section ...

  19. The extraction of $\\phi-N$ total cross section from$d(\\gamma...

    Office of Scientific and Technical Information (OSTI)

    Accepted Manuscript: The extraction of phi-N total cross section from d(gamma,pK+K-)n Title: The extraction of phi-N total cross section from d(...

  20. Determining the 239Np(n,f) cross section using the surrogate...

    Office of Scientific and Technical Information (OSTI)

    Journal Article: Determining the 239Np(n,f) cross section using the surrogate ratio method Citation Details In-Document Search Title: Determining the 239Np(n,f) cross section using ...

  1. The extraction of $\\phi-N$ total cross section from$d(\\gamma...

    Office of Scientific and Technical Information (OSTI)

    The extraction of phi-N total cross section from d(gamma,pK+K-)n Citation Details In-Document Search Title: The extraction of phi-N total cross section from ...

  2. Prospects for a measurement of the 237U(n,f) cross section at...

    Office of Scientific and Technical Information (OSTI)

    of the 237U(n,f) cross section at the LANSCE Lujan Center Citation Details In-Document Search Title: Prospects for a measurement of the 237U(n,f) cross section at the ...

  3. Sonic spectrometer and treatment system

    DOE Patents [OSTI]

    Slomka, Bogdan J.

    1997-06-03

    A novel system and method for treating an object with sonic waveforms. A traveling broad-band sonic waveform containing a broad-band of sonic frequencies is radiated at the object. A traveling reflected sonic waveform containing sonic frequencies reflected by the object is received in response to the traveling broad-band sonic waveform. A traveling transmitted sonic waveform containing sonic frequencies transmitted through the object is also received in response to the traveling broad-band sonic waveform. In a resonance mode, the frequency spectra of the broad-band and reflected sonic waveforms is analyzed so as to select one or more sonic frequencies that cause the object to resonate. An electrical resonance treatment sonic waveform containing the sonic frequencies that cause the object to resonate is then radiated at the object so as to treat the object. In an absorption mode, the frequency spectra of the electrical broad-band, reflected, and transmitted sonic waveforms is compared so as to select one or more sonic frequencies that are absorbed by the object. An electrical absorption treatment sonic waveform containing the sonic frequencies that are absorbed by the object is then radiated at the object so as to treat the object.

  4. Sonic spectrometer and treatment system

    DOE Patents [OSTI]

    Slomka, B.J.

    1997-06-03

    A novel system and method is developed for treating an object with sonic waveforms. A traveling broad-band sonic waveform containing a broad-band of sonic frequencies is radiated at the object. A traveling reflected sonic waveform containing sonic frequencies reflected by the object is received in response to the traveling broad-band sonic waveform. A traveling transmitted sonic waveform containing sonic frequencies transmitted through the object is also received in response to the traveling broad-band sonic waveform. In a resonance mode, the frequency spectra of the broad-band and reflected sonic waveforms is analyzed so as to select one or more sonic frequencies that cause the object to resonate. An electrical resonance treatment sonic waveform containing the sonic frequencies that cause the object to resonate is then radiated at the object so as to treat the object. In an absorption mode, the frequency spectra of the electrical broad-band, reflected, and transmitted sonic waveforms is compared so as to select one or more sonic frequencies that are absorbed by the object. An electrical absorption treatment sonic waveform containing the sonic frequencies that are absorbed by the object is then radiated at the object so as to treat the object. 1 fig.

  5. Radar-cross-section reduction of wind turbines. part 1.

    SciTech Connect (OSTI)

    Brock, Billy C.; Loui, Hung; McDonald, Jacob J.; Paquette, Joshua A.; Calkins, David A.; Miller, William K.; Allen, Steven E.; Clem, Paul Gilbert; Patitz, Ward E.

    2012-03-05

    In recent years, increasing deployment of large wind-turbine farms has become an issue of growing concern for the radar community. The large radar cross section (RCS) presented by wind turbines interferes with radar operation, and the Doppler shift caused by blade rotation causes problems identifying and tracking moving targets. Each new wind-turbine farm installation must be carefully evaluated for potential disruption of radar operation for air defense, air traffic control, weather sensing, and other applications. Several approaches currently exist to minimize conflict between wind-turbine farms and radar installations, including procedural adjustments, radar upgrades, and proper choice of low-impact wind-farm sites, but each has problems with limited effectiveness or prohibitive cost. An alternative approach, heretofore not technically feasible, is to reduce the RCS of wind turbines to the extent that they can be installed near existing radar installations. This report summarizes efforts to reduce wind-turbine RCS, with a particular emphasis on the blades. The report begins with a survey of the wind-turbine RCS-reduction literature to establish a baseline for comparison. The following topics are then addressed: electromagnetic model development and validation, novel material development, integration into wind-turbine fabrication processes, integrated-absorber design, and wind-turbine RCS modeling. Related topics of interest, including alternative mitigation techniques (procedural, at-the-radar, etc.), an introduction to RCS and electromagnetic scattering, and RCS-reduction modeling techniques, can be found in a previous report.

  6. Cross section measurements at LANSCE for defense, science and applications

    SciTech Connect (OSTI)

    Nelson, Ronald O.; Schwengner, R.; Zuber, K.

    2015-05-28

    The Los Alamos Neutron Science Center (LANSCE) has three neutron sources that are used for nuclear science measurements. These sources are driven by an 800 MeV proton linear accelerator and cover an energy range from sub-thermal to hundreds of MeV. Research at the facilities is performed under the auspices of a US DOE user program under which research proposals are rated for merit by a program advisory committee and are scheduled based on merit and availability of beam time. A wide variety of instruments is operated at the neutron flight paths at LANSCE including neutron detector arrays, gamma-ray detector arrays, fission fragment detectors, and charged particle detectors. These instruments provide nuclear data for multiple uses that range from increasing knowledge in fundamental science to satisfying data needs for diverse applications such as nuclear energy, global security, and industrial applications. In addition, highlights of recent research related to cross sections measurements are presented, and future research initiatives are discussed.

  7. Cross section measurements at LANSCE for defense, science and applications

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

    Nelson, Ronald O.; Schwengner, R.; Zuber, K.

    2015-05-28

    The Los Alamos Neutron Science Center (LANSCE) has three neutron sources that are used for nuclear science measurements. These sources are driven by an 800 MeV proton linear accelerator and cover an energy range from sub-thermal to hundreds of MeV. Research at the facilities is performed under the auspices of a US DOE user program under which research proposals are rated for merit by a program advisory committee and are scheduled based on merit and availability of beam time. A wide variety of instruments is operated at the neutron flight paths at LANSCE including neutron detector arrays, gamma-ray detector arrays,more » fission fragment detectors, and charged particle detectors. These instruments provide nuclear data for multiple uses that range from increasing knowledge in fundamental science to satisfying data needs for diverse applications such as nuclear energy, global security, and industrial applications. In addition, highlights of recent research related to cross sections measurements are presented, and future research initiatives are discussed.« less

  8. Partial cross sections of helium satellites at medium photon energies

    SciTech Connect (OSTI)

    Wehlitz, R.; Sellin, I.A.; Hemmers, O.

    1997-04-01

    Still of current interest is the important role of single ionization with excitation compared to single ionization alone. The coupling between the electrons and the incoming photon is a single-particle operator. Thus, an excitation in addition to an ionization, leading to a so-called satellite line in a photoelectron spectrum, is entirely due to electron-electron interaction and probes the electron correlation in the ground and final state. Therefore the authors have undertaken the study of the intensity of helium satellites He{sup +}nl (n = 2 - 6) relative to the main photoline (n = 1) as a function of photon energy at photon energies well above threshold up to 900 eV. From these results they could calculate the partial cross-sections of the helium satellites. In order to test the consistency of their satellite-to-1s ratios with published double-to-single photoionization ratios, the authors calculated the double-to-single photoionization ratio from their measured ratios using the theoretical energy-distribution curves of Chang and Poe and Le Rouzo and Dal Cappello which proved to be valid for photon energies below 120 eV. These calculated double-to-single ionization ratios agree fairly well with recent ion measurements. In the lower photon energy range the authors ratios agree better with the ratios of Doerner et al. while for higher photon energies the agreement is better with the values of Levin et al.

  9. Quantitative infrared absorption cross sections of isoprene for atmospheric measurements

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

    Brauer, C. S.; Blake, T. A.; Guenther, A. B.; Sharpe, S. W.; Sams, R. L.; Johnson, T. J.

    2014-11-19

    Isoprene (C5H8, 2-methyl-1,3-butadiene) is a volatile organic compound (VOC) and is one of the primary contributors to annual global VOC emissions. Isoprene is produced primarily by vegetation as well as anthropogenic sources, and its OH- and O3-initiated oxidations are a major source of atmospheric oxygenated organics. Few quantitative infrared studies have been reported for isoprene, limiting the ability to quantify isoprene emissions via remote or in situ infrared detection. We thus report absorption cross sections and integrated band intensities for isoprene in the 600–6500 cm-1 region. The pressure-broadened (1 atmosphere N2) spectra were recorded at 278, 298, and 323 Kmore » in a 19.94 cm path-length cell at 0.112 cm-1 resolution, using a Bruker IFS 66v/S Fourier transform infrared (FTIR) spectrometer. Composite spectra are derived from a minimum of seven isoprene sample pressures, each at one of three temperatures, and the number densities are normalized to 296 K and 1 atm.« less

  10. Application of nuclear models to neutron nuclear cross section calculations

    SciTech Connect (OSTI)

    Young, P.G.

    1982-01-01

    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).

  11. Elastic Cross Sections for Electron Collisions with Molecules Relevant to Plasma Processing

    SciTech Connect (OSTI)

    Yoon, J.-S.; Song, M.-Y.; Kato, H.; Hoshino, M.; Tanaka, H.; Brunger, M. J.; Buckman, S. J.; Cho, H.

    2010-09-15

    Absolute electron-impact cross sections for molecular targets, including their radicals, are important in developing plasma reactors and testing various plasma processing gases. Low-energy electron collision data for these gases are sparse and only the limited cross section data are available. In this report, elastic cross sections for electron-polyatomic molecule collisions are compiled and reviewed for 17 molecules relevant to plasma processing. Elastic cross sections are essential for the absolute scale conversion of inelastic cross sections, as well as for testing computational methods. Data are collected and reviewed for elastic differential, integral, and momentum transfer cross sections and, for each molecule, the recommended values of the cross section are presented. The literature has been surveyed through early 2010.

  12. Simultaneous evaluation of interrelated cross sections by generalized least-squares and related data file requirements

    SciTech Connect (OSTI)

    Poenitz, W.P.

    1984-10-25

    Though several cross sections have been designated as standards, they are not basic units and are interrelated by ratio measurements. Moreover, as such interactions as /sup 6/Li + n and /sup 10/B + n involve only two and three cross sections respectively, total cross section data become useful for the evaluation process. The problem can be resolved by a simultaneous evaluation of the available absolute and shape data for cross sections, ratios, sums, and average cross sections by generalized least-squares. A data file is required for such evaluation which contains the originally measured quantities and their uncertainty components. Establishing such a file is a substantial task because data were frequently reported as absolute cross sections where ratios were measured without sufficient information on which reference cross section and which normalization were utilized. Reporting of uncertainties is often missing or incomplete. The requirements for data reporting will be discussed.

  13. Total reaction cross sections in CEM and MCNP6 at intermediate energies

    SciTech Connect (OSTI)

    Kerby, Leslie M.; Mashnik, Stepan G.

    2015-05-14

    Accurate total reaction cross section models are important to achieving reliable predictions from spallation and transport codes. The latest version of the Cascade Exciton Model (CEM) as incorporated in the code CEM03.03, and the Monte Carlo N-Particle transport code (MCNP6), both developed at Los Alamos National Laboratory (LANL), each use such cross sections. Having accurate total reaction cross section models in the intermediate energy region (50 MeV to 5 GeV) is very important for different applications, including analysis of space environments, use in medical physics, and accelerator design, to name just a few. The current inverse cross sections used in the preequilibrium and evaporation stages of CEM are based on the Dostrovsky et al. model, published in 1959. Better cross section models are now available. Implementing better cross section models in CEM and MCNP6 should yield improved predictions for particle spectra and total production cross sections, among other results.

  14. Total Cross Sections as a Surrogate for Neutron Capture: An Opportunity to Accurately Constrain (n,γ) Cross Sections for Nuclides Beyond the Reach of Direct Measurements

    SciTech Connect (OSTI)

    Koehler, Paul E.

    2014-03-05

    There are many (n,γ) cross sections of great interest to radiochemical diagnostics and to nuclear astrophysics which are beyond the reach of current measurement techniques, and likely to remain so for the foreseeable future. In contrast, total neutron cross sections currently are feasible for many of these nuclides and provide almost all the information needed to accurately calculate the (n,γ) cross sections via the nuclear statistical model (NSM). I demonstrate this for the case of 151Sm; NSM calculations constrained using average resonance parameters obtained from total cross section measurements made in 1975, are in excellent agreement with recent 151Sm (n,γ) measurements across a wide range of energy. Furthermore, I demonstrate through simulations that total cross section measurements can be made at the Manuel Lujan Jr. Neutron Scattering Center at the Los Alamos Neutron Science Center for samples as small as 10μg. Samples of this size should be attainable for many nuclides of interest. Finally, I estimate that over half of the radionuclides identified ∼20 years ago as having (n,γ) cross sections of importance to s-process nucleosynthesis studies (24/43) and radiochemical diagnostics (11/19), almost none of which have been measured, can be constrained using this technique.

  15. Generation of Collapsed Cross Sections for Hatch 1 Cycles 1-3

    SciTech Connect (OSTI)

    Ade, Brian J

    2012-11-01

    Under NRC JCN V6361, Oak Ridge National Laboratory (ORNL) was tasked to develop and run SCALE/TRITON models for generation of collapsed few-group cross sections and to convert the cross sections to PMAXS format using the GENPMAXS conversion utility for use in PARCS/PATHS simulations of Hatch Unit 1, cycles 1-3. This letter report documents the final models used to produce the Hatch collapsed cross sections.

  16. Modeled Neutron Induced Nuclear Reaction Cross Sections for Radiochemistry in the region of Iriduim and Gold

    SciTech Connect (OSTI)

    Hoffman, R D; Dietrich, F S; Kelley, K; Escher, J; Bauer, R; Mustafa, M

    2008-02-26

    We have developed a set of modeled nuclear reaction cross sections for use in radiochemical diagnostics. Systematics for the input parameters required by the Hauser-Feshbach statistical model were developed and used to calculate neutron induced nuclear reaction cross sections for targets ranging from osmium (Z = 76) to gold (Z = 79). Of particular interest are the cross sections on Ir and Au including reactions on isomeric targets.

  17. Neutron-Induced Fission Cross Section Measurements for Uranium Isotopes and

    Office of Scientific and Technical Information (OSTI)

    Other Actinides at LANSCE (Conference) | SciTech Connect Neutron-Induced Fission Cross Section Measurements for Uranium Isotopes and Other Actinides at LANSCE Citation Details In-Document Search Title: Neutron-Induced Fission Cross Section Measurements for Uranium Isotopes and Other Actinides at LANSCE A well established program of neutron-induced fission cross section measurement at Los Alamos Neutron Science Center (LANSCE) is supporting the Fuel Cycle Research program (FC R&D). The

  18. Inclusive w and z cross section measurements at the Fermilab Tevatron

    SciTech Connect (OSTI)

    Martin, Victoria; /Northwestern U.

    2004-12-01

    The present recent measurements of the inclusive cross section of W and Z bosons from Run II of the Fermilab Tevatron collider.

  19. MiniBooNE Charged Current Charged Pion Cross Section Data Release

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

    Muon Neutrino-Induced Charged-Current Charged Pion Production Cross Sections on Mineral Oil at Enu~1 GeV", arXiv:1011.3572 [hep-ex], submitted to Phys. Rev. D. The following MiniBooNE information for the 2010 CC π+ cross section paper is made available to the public. Tables A root file containing histograms of all of the cross section results in the paper can be found here. A text file of the cross section results can be found here. The MiniBooNE muon neutrino flux distribution can be

  20. AMPX-II P3 123-Group Neutron Cross Section Master Interface Library.

    Energy Science and Technology Software Center (OSTI)

    1991-01-30

    Version 00 The cross section data can be used for criticality calculations. They have been tested with the KENO-IV Monte Carlo code.

  1. Soda Lake Well Lithology Data and Geologic Cross-Sections (Dataset...

    Office of Scientific and Technical Information (OSTI)

    Comprehensive catalogue of drill-hole data in spreadsheet, shapefile, and Geosoft database ... area; Well Lithology Data; Drill-hole database; Geologic Cross-Sections; Gravity ...

  2. Measurements of Neutron Induced Cross Sections at the Oak Ridge Electron Linear Accelerator

    SciTech Connect (OSTI)

    Guber, K.H.; Harvey, J.A.; Hill, N.W.; Koehler, P.E.; Leal, L.C.; Sayer, R.O.; Spencer, R.R.

    1999-09-20

    We have used the Oak Ridge Electron Linear Accelerator (ORELA) to measure neutron total and the fission cross sections of 233U in the energy range from 0.36 eV to ~700 keV. We report average fission and total cross sections. Also, we measured the neutron total cross sections of 27Al and Natural chlorine as well as the capture cross section of Al over an energy range from 100 eV up to about 400 keV.

  3. New Tools to Prepare ACE Cross-section Files for MCNP Analytic...

    Office of Scientific and Technical Information (OSTI)

    Title: New Tools to Prepare ACE Cross-section Files for MCNP Analytic Test Problems Authors: Brown, Forrest B. 1 + Show Author Affiliations Los Alamos National Laboratory ...

  4. Photoionization and photoabsorption cross sections for the aluminum iso-nuclear sequence

    SciTech Connect (OSTI)

    Witthoeft, M.C.; Garca, J.; Kallman, T.R.; Palmeri, P.; Quinet, P.; INPAS, Universit de Lige, B-4000 Lige

    2013-01-15

    K-shell photoionization and photoabsorption cross sections are presented for Li-like to Na-like Al. The calculations are performed using the BreitPauli R-matrix method where the effects of radiation and Auger dampings are included. We provide electronic data files for the raw cross sections as well as those convolved with a Gaussian of width ?E/E=10{sup ?4}. In addition to total cross sections for photoabsorption and photoionization, partial cross sections are available for photoionization.

  5. Measurements of production cross sections of 10Be and 26Al by...

    Office of Scientific and Technical Information (OSTI)

    Measurements of production cross sections of 10Be and 26Al by 120 GeV and 392 MeV proton ... Title: Measurements of production cross sections of 10Be and 26Al by 120 GeV and 392 MeV ...

  6. MUXS: a code to generate multigroup cross sections for sputtering calculations

    SciTech Connect (OSTI)

    Hoffman, T.J.; Robinson, M.T.; Dodds, H.L. Jr.

    1982-10-01

    This report documents MUXS, a computer code to generate multigroup cross sections for charged particle transport problems. Cross sections generated by MUXS can be used in many multigroup transport codes, with minor modifications to these codes, to calculate sputtering yields, reflection coefficients, penetration distances, etc.

  7. PROBLEM DEPENDENT DOPPLER BROADENING OF CONTINUOUS ENERGY CROSS SECTIONS IN THE KENO MONTE CARLO COMPUTER CODE

    SciTech Connect (OSTI)

    Hart, S. W. D.; Maldonado, G. Ivan; Celik, Cihangir; Leal, Luiz C

    2014-01-01

    For many Monte Carlo codes cross sections are generally only created at a set of predetermined temperatures. This causes an increase in error as one moves further and further away from these temperatures in the Monte Carlo model. This paper discusses recent progress in the Scale Monte Carlo module KENO to create problem dependent, Doppler broadened, cross sections. Currently only broadening the 1D cross sections and probability tables is addressed. The approach uses a finite difference method to calculate the temperature dependent cross-sections for the 1D data, and a simple linear-logarithmic interpolation in the square root of temperature for the probability tables. Work is also ongoing to address broadening theS (alpha , beta) tables. With the current approach the temperature dependent cross sections are Doppler broadened before transport starts, and, for all but a few isotopes, the impact on cross section loading is negligible. Results can be compared with those obtained by using multigroup libraries, as KENO currently does interpolation on the multigroup cross sections to determine temperature dependent cross-sections. Current results compare favorably with these expected results.

  8. Using a Time Projection Chamber to Measure High Precision Neutron-Induced Fission Cross Sections

    SciTech Connect (OSTI)

    Manning, Brett

    2015-08-06

    2014 LANSCE run cycle data will provide a preliminary 239Pu(n,f) cross section and will quantify uncertainties: PID and Target/beam non-uniformities. Continued running during the 2015 LANSCE run cycle: Thin targets to see both fission fragments and 239Pu(n,f) cross section and fully quantified uncertainties

  9. Total reaction cross sections in CEM and MCNP6 at intermediate energies

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

    Kerby, Leslie M.; Mashnik, Stepan G.

    2015-05-14

    Accurate total reaction cross section models are important to achieving reliable predictions from spallation and transport codes. The latest version of the Cascade Exciton Model (CEM) as incorporated in the code CEM03.03, and the Monte Carlo N-Particle transport code (MCNP6), both developed at Los Alamos National Laboratory (LANL), each use such cross sections. Having accurate total reaction cross section models in the intermediate energy region (50 MeV to 5 GeV) is very important for different applications, including analysis of space environments, use in medical physics, and accelerator design, to name just a few. The current inverse cross sections used inmore » the preequilibrium and evaporation stages of CEM are based on the Dostrovsky et al. model, published in 1959. Better cross section models are now available. Implementing better cross section models in CEM and MCNP6 should yield improved predictions for particle spectra and total production cross sections, among other results.« less

  10. Measurement of the inclusive and dijet cross-sections of b-jets in pp collisions at root s=7 TeV with the ATLAS detector

    SciTech Connect (OSTI)

    Aad, G.; Abbott, B; Abdallah, J; Abdelalim, AA; Abdesselam, A; Abdinov, O; Abi, B; Abolins, M; Abramowicz, H; Abreu, H; Acerbi, E; Acharya, BS; Adams, DL; Addy, TN; Adelman, J; Aderholz, M; Adomeit, S; Adragna, P; Adye, T; Aefsky, S; Aguilar-Saavedra, JA; A

    2011-12-01

    The inclusive and dijet production cross-sections have been measured for jets containing b-hadrons (b-jets) in proton-proton collisions at a centre-of-mass energy of {radical}s = 7 TeV, using the ATLAS detector at the LHC. The measurements use data corresponding to an integrated luminosity of 34 pb{sup -1}. The b-jets are identified using either a lifetime-based method, where secondary decay vertices of b-hadrons in jets are reconstructed using information from the tracking detectors, or a muon-based method where the presence of a muon is used to identify semileptonic decays of b-hadrons inside jets. The inclusive b-jet cross-section is measured as a function of transverse momentum in the range 20 < p{sub T} < 400 GeV and rapidity in the range |y| < 2.1. The b{bar b}-dijet cross-section is measured as a function of the dijet invariant mass in the range 110 < m{sub jj} < 760 GeV, the azimuthal angle difference between the two jets and the angular variable {chi} in two dijet mass regions. The results are compared with next-to-leading-order QCD predictions. Good agreement is observed between the measured cross-sections and the predictions obtained using POWHEG + Pythia. MC{at}NLO + Herwig shows good agreement with the measured b{bar b}-dijet cross-section. However, it does not reproduce the measured inclusive cross-section well, particularly for central b-jets with large transverse momenta.

  11. MiniBooNE Neutral Current Elastic Cross Section Data Release

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

    the Neutrino Neutral-Current Elastic Differential Cross Section",arXiv:1007.4730 [hep-ex], Phys. Rev. D82, 092005 (2010) The following MiniBooNE information for the 2010 neutral current elastic cross section paper is made available to the public. MiniBooNE neutral current elastic cross-section results in the "paper" are reported in the true energy after the unsmearing of detector resolution and efficiency effects. In addition, here we present alternative results in the

  12. Covariance of Neutron Cross Sections for {sup 16}O through R-matrix Analysis

    SciTech Connect (OSTI)

    Kunieda, S.; Kawano, T.; Paris, M.; Hale, G.M.; Shibata, K.; Fukahori, T.

    2015-01-15

    Through the R-matrix analysis, neutron cross sections as well as the covariance are estimated for {sup 16}O in the resolved resonance range. Although we consider the current results are still preliminary, we present the summary of the cross section analysis and the results of data uncertainty/covariance, including those for the differential cross sections. It is found that the values obtained highlight consequences of nature in the theory as well as knowledge from measurements, which gives a realistic quantification of evaluated nuclear data covariances.

  13. Measurement of the antineutrino neutral-current elastic differential cross section

    SciTech Connect (OSTI)

    Aguilar-Arevalo, A.  A.; Brown, B.  C.; Bugel, L.; Cheng, G.; Church, E.  D.; Conrad, J.  M.; Dharmapalan, R.; Djurcic, Z.; Finley, D.  A.; Ford, R.; Garcia, F.  G.; Garvey, G.  T.; Grange, J.; Huelsnitz, W.; Ignarra, C.; Imlay, R.; Johnson, R.  A.; Karagiorgi, G.; Katori, T.; Kobilarcik, T.; Louis, W.  C.; Mariani, C.; Marsh, W.; Mills, G.  B.; Mirabal, J.; Moore, C.  D.; Mousseau, J.; Nienaber, P.; Osmanov, B.; Pavlovic, Z.; Perevalov, D.; Polly, C.  C.; Ray, H.; Roe, B.  P.; Russell, A.  D.; Shaevitz, M.  H.; Spitz, J.; Stancu, I.; Tayloe, R.; Van de Water, R.  G.; Wascko, M.  O.; White, D.  H.; Wickremasinghe, D.  A.; Zeller, G.  P.; Zimmerman, E.  D.

    2015-01-08

    We report the measurement of the flux-averaged antineutrino neutral current elastic scattering cross section (dσν-barN→ν-barN/dQ2) on CH2 by the MiniBooNE experiment using the largest sample of antineutrino neutral current elastic candidate events ever collected. The ratio of the antineutrino to neutrino neutral current elastic scattering cross sections and a ratio of the antineutrino neutral current elastic to antineutrino charged current quasi elastic cross sections are also presented.

  14. Measurement of the antineutrino neutral-current elastic differential cross section

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

    Aguilar-Arevalo, A.  A.; Brown, B.  C.; Bugel, L.; Cheng, G.; Church, E.  D.; Conrad, J.  M.; Dharmapalan, R.; Djurcic, Z.; Finley, D.  A.; Ford, R.; et al

    2015-01-08

    We report the measurement of the flux-averaged antineutrino neutral current elastic scattering cross section (dσν-barN→ν-barN/dQ2) on CH2 by the MiniBooNE experiment using the largest sample of antineutrino neutral current elastic candidate events ever collected. The ratio of the antineutrino to neutrino neutral current elastic scattering cross sections and a ratio of the antineutrino neutral current elastic to antineutrino charged current quasi elastic cross sections are also presented.

  15. Verification of the MCNP (TM) Perturbation Correction Feature for Cross-Section Dependent Tallies

    SciTech Connect (OSTI)

    A. K. Hess; G. W. McKinney; J. S. Hendricks; L. L. Carter

    1998-10-01

    The Monte Carlo N-Particle Transport Code MCNP version 4B perturbation capability has been extended to cross-section dependent tallies and to the track-length estimate of Iqff in criticality problems. We present the complete theory of the MCNP perturbation capability including the correction to MCNP4B which enables cross-section dependent perturbation tallies. We also present the MCNP interface as an upgrade to the MCNP4B manual. Finally, we present test results demonstrating the validity of the perturbation capability in MCNP, particularly cross-section dependent problems.

  16. Diboson cross sections at s**(1/2) = 1.96-TeV

    SciTech Connect (OSTI)

    Askew, A.W.; /Fermilab

    2005-05-01

    A brief survey of the results on diboson production at the Tevatron is presented. Measured cross sections for W{gamma}, Z{gamma}, WW, and limits on WZ/ZZ are summarized.

  17. ICSBEP Criticality Benchmark Eigenvalues with ENDF/B-VII.1 Cross Sections

    SciTech Connect (OSTI)

    Kahler, Albert C. III; MacFarlane, Robert

    2012-06-28

    We review MCNP eigenvalue calculations from a suite of International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook evaluations with the recently distributed ENDF/B-VII.1 cross section library.

  18. Error Assessment of Homogenized Cross Sections Generation for Whole Core Neutronic Calculation

    SciTech Connect (OSTI)

    Hursin, Mathieu; Kochunas, Brendan; Downar, Thomas J.

    2007-10-26

    The objective of the work here was to assess the errors introduced by using 2D, few group homogenized cross sections to perform neutronic analysis of BWR problems with significant axial heterogeneities. The 3D method of characteristics code DeCART is used to generate 2-group assembly homogenized cross sections first using a conventional 2D lattice model and then using a full 3D solution of the assembly. A single BWR fuel assembly model based on an advanced BWR lattice design is used with a typical void distribution applied to the fuel channel coolant. This model is validated against an MCNP model. A comparison of the cross sections is performed for the assembly homogenized planar cross sections from the DeCART 3D and DeCART 2D solutions.

  19. Measurements of the t-tbar production cross section in lepton...

    Office of Scientific and Technical Information (OSTI)

    Measurements of the t-tbar production cross section in lepton+jets final states in pp ... Citation Details In-Document Search Title: Measurements of the t-tbar production cross ...

  20. Empirical Fit to Inelastic Electron-Deuteron and Electron-Neutron Resonance Region Transverse Cross Sections

    SciTech Connect (OSTI)

    Peter Bosted; M. E. Christy

    2007-11-08

    An empirical fit is described to measurements of inclusive inelastic electron-deuteron cross sections in the kinematic range of four-momentum transfer $0 \\le Q^2<10$ GeV$^2$ and final state invariant mass $1.2<3$ GeV. The deuteron fit relies on a fit of the ratio $R_p$ of longitudinal to transverse cross sections for the proton, and the assumption $R_p=R_n$. The underlying fit parameters describe the average cross section for proton and neutron, with a plane-wave impulse approximation (PWIA) used to fit to the deuteron data. Pseudo-data from MAID 2007 were used to constrain the average nucleon cross sections for $W<1.2$ GeV. The mean deviation of data from the fit is 3\\%, with less than 5\\% of the data points deviating from the fit by more than 10\\%.

  1. Measurement of cross sections for the Cu-63(alpha,gamma)Ga-67...

    Office of Scientific and Technical Information (OSTI)

    Title: Measurement of cross sections for the Cu-63(alpha,gamma)Ga-67 reaction from 5.9-8.7 MeV Authors: Basunia, M S ; Norman, E B ; Shugart, H A ; Smith, A R ; Dolinski, M J ; ...

  2. MiniBooNE NC 1π0 Cross Section Data Release

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

    νμ and ν̅μ induced neutral current single π0 production cross sections on mineral oil at Eν~O(1 GeV)", arXiv:0911.2063 [hep-ex], Phys. Rev. D81, 013005 (2010) The following MiniBooNE information from the 2009 NC 1π0 cross section paper is made available to the public: Neutrino Mode Running νμ NC 1π0 pπ0 Differential Cross Section 1D array of bin boundaries partitioning the momentum of the π0 1D array of the value of the differential cross section in each bin in units of 10-40

  3. Average Neutron Total Cross Sections in the Unresolved Energy Range From ORELA High Resolutio Transmission Measurements

    SciTech Connect (OSTI)

    Derrien, H

    2004-05-27

    Average values of the neutron total cross sections of {sup 233}U, {sup 235}U, {sup 238}U, and {sup 239}Pu have been obtained in the unresolved resonance energy range from high-resolution transmission measurements performed at ORELA in the past two decades. The cross sections were generated by correcting the effective total cross sections for the self-shielding effects due to the resonance structure of the data. The self-shielding factors were found by calculating the effective and true cross sections with the computer code SAMMY for the same Doppler and resolution conditions as for the transmission measurements, using an appropriate set of resonance parameters. Our results are compared to results of previous measurements and to the current ENDF/B-VI data.

  4. Measurement of Cross Sections for the 63Cu(alpha,gamma)67Ga Reaction...

    Office of Scientific and Technical Information (OSTI)

    Title: Measurement of Cross Sections for the 63Cu(alpha,gamma)67Ga Reaction from 5.9-8.7 MeV Authors: Basunia, M S ; Norman, E B ; Shugart, H A ; Smith, A R ; Dolinski, M J ; ...

  5. MiniBooNE Charged Current Neutral Pion Cross Section Data Release

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

    of the central-value differential cross-section measurement as a function of 0 angle as found in Figure 14 and Table 11 of the paper. Contact Information For...

  6. Differential two-body compound nuclear cross section, including the width-fluctuation corrections

    SciTech Connect (OSTI)

    Brown, D.; Herman, M.

    2014-09-02

    We figure out the compound angular differential cross sections, following mainly Fröbrich and Lipperheide, but with the angular momentum couplings that make sense for optical model work. We include the width-fluctuation correction along with calculations.

  7. ENDF/B-VII.1 Beta4 Temperature Dependent Cross Section Library.

    Energy Science and Technology Software Center (OSTI)

    2011-11-13

    Version 01 As distributed, the ENDF/B-VII.1 data includes cross sections represented in the form of a combination of resonance parameters and/or tabulated energy dependent cross sections, nominally at 0 Kelvin temperature. For use in applications the ENDF/B-VII.1 library has been processed into the form of temperature dependent cross sections at eight neutron reactor like temperatures, between 0 and 2100 Kelvin, in steps of 300 Kelvin (the exception being 293.6 Kelvin, for exact room temperature atmore » 20 Celsius). It has also been processed to five astrophysics like temperatures—1, 10, and 100 eV; and 1 and 10 keV. For reference purposes, 300 Kelvin is approximately 1/40 eV, so that 1 eV is approximately 12,000 Kelvin. At each temperature the cross sections are tabulated and linearly interpolable in energy.« less

  8. ENDF/B-VII.1 Beta4 Temperature Dependent Cross Section Library.

    Energy Science and Technology Software Center (OSTI)

    2011-07-22

    Version 00 As distributed, the ENDF/B-VII.1 data includes cross sections represented in the form of a combination of resonance parameters and/or tabulated energy dependent cross sections, nominally at 0 Kelvin temperature. For use in applications the ENDF/B-VII.1 library has been processed into the form of temperature dependent cross sections at eight neutron reactor like temperatures, between 0 and 2100 Kelvin, in steps of 300 Kelvin (the exception being 293.6 Kelvin, for exact room temperature atmore » 20 Celsius). It has also been processed to five astrophysics like temperatures—1, 10, and 100 eV; and 1 and 10 keV. For reference purposes, 300 Kelvin is approximately 1/40 eV, so that 1 eV is approximately 12,000 Kelvin. At each temperature the cross sections are tabulated and linearly interpolable in energy.« less

  9. Prospects for a measurement of the 237U(n,f) cross section at...

    Office of Scientific and Technical Information (OSTI)

    Prospects for a measurement of the 237U(n,f) cross section at the LANSCE Lujan Center Citation Details In-Document Search Title: Prospects for a measurement of the 237U(n,f) cross ...

  10. Assessment of Fission Product Cross-Section Data for Burnup Credit Applications

    SciTech Connect (OSTI)

    Leal, Luiz C; Derrien, Herve; Dunn, Michael E; Mueller, Don

    2007-12-01

    Past efforts by the Department of Energy (DOE), the Electric Power Research Institute (EPRI), the Nuclear Regulatory Commission (NRC), and others have provided sufficient technical information to enable the NRC to issue regulatory guidance for implementation of pressurized-water reactor (PWR) burnup credit; however, consideration of only the reactivity change due to the major actinides is recommended in the guidance. Moreover, DOE, NRC, and EPRI have noted the need for additional scientific and technical data to justify expanding PWR burnup credit to include fission product (FP) nuclides and enable burnup credit implementation for boiling-water reactor (BWR) spent nuclear fuel (SNF). The criticality safety assessment needed for burnup credit applications will utilize computational analyses of packages containing SNF with FP nuclides. Over the years, significant efforts have been devoted to the nuclear data evaluation of major isotopes pertinent to reactor applications (i.e., uranium, plutonium, etc.); however, efforts to evaluate FP cross-section data in the resonance region have been less thorough relative to actinide data. In particular, resonance region cross-section measurements with corresponding R-matrix resonance analyses have not been performed for FP nuclides. Therefore, the objective of this work is to assess the status and performance of existing FP cross-section and cross-section uncertainty data in the resonance region for use in burnup credit analyses. Recommendations for new cross-section measurements and/or evaluations are made based on the data assessment. The assessment focuses on seven primary FP isotopes (103Rh, 133Cs, 143Nd, 149Sm, 151Sm, 152Sm, and 155Gd) that impact reactivity analyses of transportation packages and two FP isotopes (153Eu and 155Eu) that impact prediction of 155Gd concentrations. Much of the assessment work was completed in 2005, and the assessment focused on the latest FP cross-section evaluations available in the

  11. MiniBooNE NC 1?0 Cross Section Data Release

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

    0 production cross sections on mineral oil at EO(1 GeV)", arXiv:0911.2063 hep-ex, Phys. Rev. D81, 013005 (2010) The following MiniBooNE information from the 2009 NC 10...

  12. Subsurface cross section of lower Paleozoic rocks, Powder River basin, Wyoming and Montana

    SciTech Connect (OSTI)

    Macke, D.L.

    1988-07-01

    The Powder River basin is one of the most actively explored Rocky Mountain basins for hydrocarbons, yet the lower Paleozoic (Cambrian through Mississippian) rocks of this interval remain little studied. As a part of a program studying the evolution of sedimentary basins, approximately 3200 km of cross section, based on more than 50 combined geophysical and lithologic logs, have been constructed covering an area of about 200,000 km/sup 2/. The present-day basin is a Cenozoic structural feature located between the stable interior of the North American craton and the Cordilleran orogenic belt. At various times during the early Paleozoic, the basin area was not distinguishable from either the stable craton, the Williston basin, the Central Montana trough, or the Cordilleran miogeocline. Both deposition and preservation in the basin have been greatly influenced by the relative uplift of the Transcontinental arch. Shows of oil and dead oil in well cuttings confirm that hydrocarbons have migrated through at least parts of the basin's lower Paleozoic carbonate section. These rocks may have been conduits for long-distance migration of hydrocarbons as early as Late Cretaceous, based on (1) the probable timing of thermal maturation of hydrocarbon-source rocks within the basin area and to the west, (2) the timing of Laramide structural events, (3) the discontinuous nature of the reservoirs in the overlying, highly productive Pennsylvanian-Permian Minnelusa Formation, and (4) the under-pressuring observed in some Minnelusa oil fields. Vertical migration into the overlying reservoirs could have been through deep fractures within the basin, represented by major lineament systems. Moreover, the lower Paleozoic rocks themselves may also be hydrocarbon reservoirs.

  13. On two-parameter models of photon cross sections: Application to dual-energy CT imaging

    SciTech Connect (OSTI)

    Williamson, Jeffrey F.; Li Sicong; Devic, Slobodan; Whiting, Bruce R.; Lerma, Fritz A.

    2006-11-15

    The goal of this study is to evaluate the theoretically achievable accuracy in estimating photon cross sections at low energies (20-1000 keV) from idealized dual-energy x-ray computed tomography (CT) images. Cross-section estimation from dual-energy measurements requires a model that can accurately represent photon cross sections of any biological material as a function of energy by specifying only two characteristic parameters of the underlying material, e.g., effective atomic number and density. This paper evaluates the accuracy of two commonly used two-parameter cross-section models for postprocessing idealized measurements derived from dual-energy CT images. The parametric fit model (PFM) accounts for electron-binding effects and photoelectric absorption by power functions in atomic number and energy and scattering by the Klein-Nishina cross section. The basis-vector model (BVM) assumes that attenuation coefficients of any biological substance can be approximated by a linear combination of mass attenuation coefficients of two dissimilar basis substances. Both PFM and BVM were fit to a modern cross-section library for a range of elements and mixtures representative of naturally occurring biological materials (Z=2-20). The PFM model, in conjunction with the effective atomic number approximation, yields estimated the total linear cross-section estimates with mean absolute and maximum error ranges of 0.6%-2.2% and 1%-6%, respectively. The corresponding error ranges for BVM estimates were 0.02%-0.15% and 0.1%-0.5%. However, for photoelectric absorption frequency, the PFM absolute mean and maximum errors were 10.8%-22.4% and 29%-50%, compared with corresponding BVM errors of 0.4%-11.3% and 0.5%-17.0%, respectively. Both models were found to exhibit similar sensitivities to image-intensity measurement uncertainties. Of the two models, BVM is the most promising approach for realizing dual-energy CT cross-section measurement.

  14. Measuring n-N Deep Inelastic Cross Sections at MiniBooNE

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

    + Cross Section Results from MiniBooNE Mike Wilking TRIUMF / University of Colorado NuInt 22 May 2009 CCπ + in Oscillation Experiments  The next generation of ν oscillation experiments lie at low, mostly unexplored ν energies  CCQE is the signal process for oscillation measurements  At these energies, CCπ + is the dominant charged-current background T2K NOνA CCπ + CCQE DIS Charged Current Cross Sections Previous CCπ + Measurements  The plot shows previous absolute cross

  15. Measurement of Muon Neutrino and Antineutrino Induced Single Neutral Pion Production Cross Sections

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

    Measurement of Muon Neutrino and Antineutrino Induced Single Neutral Pion Production Cross Sections Colin E. Anderson 2011 Elucidating the nature of neutrino oscillation continues to be a goal in the vanguard of the ef- forts of physics experiment. As neutrino oscillation searches seek an increasingly elusive sig- nal, a thorough understanding of the possible backgrounds becomes ever more important. Measurements of neutrino-nucleus interaction cross sections are key to this understand- ing.

  16. Fission theory: Its relevance to the nuclear cross section data base

    SciTech Connect (OSTI)

    Lynn, J.E.

    1989-01-01

    The development of fission reaction theory in relation to its predictive power in the calculation of neutron cross-sections is reviewed. The topics covered include the transition state spectrum and the channel theory; the discovery of complex topography in the fission barrier and the consequences of intermediate structure in fission cross-sections; the evidence of experimental data in parameterizing the fission barrier; and the role of other aspects of collective nuclear motion in controlling fission reaction rates. 51 refs., 6 figs.

  17. Validity of Hansen-Roach cross sections in low-enriched uranium systems

    SciTech Connect (OSTI)

    Busch, R.D. ); O'Dell, R.D. )

    1991-01-01

    Within the nuclear criticality safety community, the Hansen-Roach 16 group cross section set has been the standard'' for use in k{sub eff} calculations over the past 30 years. Yet even with its widespread acceptance, there are still questions about its validity and adequacy, about the proper procedure for calculating the potential scattering cross section, {sigma}{sub p}, for uranium and plutonium, and about the concept of resonance self shielding and its impact on cross sections. This paper attempts to address these questions. It provides a brief background on the Hansen-Roach cross sections. Next is presented a review of resonances in cross sections, self shielding of these resonances, and the use of {sigma}{sub p} to characterize resonance self shielding. Three prescriptions for calculating {sigma}{sub p} are given. Finally, results of several calculations of k{sub eff} on low-enriched uranium systems are provided to confirm the validity of the Hansen-Roach cross sections when applied to such systems.

  18. Many-Group Cross-Section Adjustment Techniques for Boiling Water Reactor Adaptive Simulation

    SciTech Connect (OSTI)

    Jessee, Matthew Anderson

    2011-01-01

    Computational capability has been developed to adjust multigroup neutron cross sections, including self-shielding correction factors, to improve the fidelity of boiling water reactor (BWR) core modeling and simulation. The method involves propagating multigroup neutron cross-section uncertainties through various BWR computational models to evaluate uncertainties in key core attributes such as core k{sub eff}, nodal power distributions, thermal margins, and in-core detector readings. Uncertainty-based inverse theory methods are then employed to adjust multigroup cross sections to minimize the disagreement between BWR core modeling predictions and observed (i.e., measured) plant data. For this paper, observed plant data are virtually simulated in the form of perturbed three-dimensional nodal power distributions with the perturbations sized to represent actual discrepancies between predictions and real plant data. The major focus of this work is to efficiently propagate multigroup neutron cross-section uncertainty through BWR lattice physics and core simulator calculations. The data adjustment equations are developed using a subspace approach that exploits the ill-conditioning of the multigroup cross-section covariance matrix to minimize computation and storage burden. Tikhonov regularization is also employed to improve the conditioning of the data adjustment equations. Expressions are also provided for posterior covariance matrices of both the multigroup cross-section and core attributes uncertainties.

  19. Calculation of cross sections for binary reactions between heavy ion projectiles and heavy actinide targets

    SciTech Connect (OSTI)

    Hoffman, D.C.; Hoffman, M.M.

    1990-11-01

    The computer program, described in this report, is identified as PWAVED5. It was developed to calculate cross sections for nucleon transfer reactions in low energy heavy ion bombardments. The objective was to calculate cross sections that agree with experimental results for ions of different charge and mass and to develop a predictive capability. It was undertaken because previous heavy ion calculations, for which programs were readily available, appeared to focus primarily on reactions resulting in compound nucleus formation and were not particularly applicable to calculations of binary reaction cross sections at low interaction energies. There are to principal areas in which this computation differs from several other partial wave calculations of heavy-ion reaction cross sections. First, this program is designed specifically to calculate cross sections for nucleon exchange interactions and to exclude interactions that are expected to result in fusion of the two nuclei. A second major difference in this calculation is the use of a statistical distribution to assign the total interaction cross section to individual final mass states.

  20. Mixed Legendre moments and discrete scattering cross sections for anisotropy representation

    SciTech Connect (OSTI)

    Calloo, A.; Vidal, J. F.; Le Tellier, R.; Rimpault, G.

    2012-07-01

    This paper deals with the resolution of the integro-differential form of the Boltzmann transport equation for neutron transport in nuclear reactors. In multigroup theory, deterministic codes use transfer cross sections which are expanded on Legendre polynomials. This modelling leads to negative values of the transfer cross section for certain scattering angles, and hence, the multigroup scattering source term is wrongly computed. The first part compares the convergence of 'Legendre-expanded' cross sections with respect to the order used with the method of characteristics (MOC) for Pressurised Water Reactor (PWR) type cells. Furthermore, the cross section is developed using piecewise-constant functions, which better models the multigroup transfer cross section and prevents the occurrence of any negative value for it. The second part focuses on the method of solving the transport equation with the above-mentioned piecewise-constant cross sections for lattice calculations for PWR cells. This expansion thereby constitutes a 'reference' method to compare the conventional Legendre expansion to, and to determine its pertinence when applied to reactor physics calculations. (authors)

  1. Sonic Corporation | Open Energy Information

    Open Energy Info (EERE)

    to: navigation, search Name: Sonic Corporation Place: Stratford, Connecticut Product: Provider of mixing equipment, high pressure homogenizers, emulsifying equipment, colloid mills...

  2. Sonication standard laboratory module

    DOE Patents [OSTI]

    Beugelsdijk, Tony; Hollen, Robert M.; Erkkila, Tracy H.; Bronisz, Lawrence E.; Roybal, Jeffrey E.; Clark, Michael Leon

    1999-01-01

    A standard laboratory module for automatically producing a solution of cominants from a soil sample. A sonication tip agitates a solution containing the soil sample in a beaker while a stepper motor rotates the sample. An aspirator tube, connected to a vacuum, draws the upper layer of solution from the beaker through a filter and into another beaker. This beaker can thereafter be removed for analysis of the solution. The standard laboratory module encloses an embedded controller providing process control, status feedback information and maintenance procedures for the equipment and operations within the standard laboratory module.

  3. Cross section standards for neutron-induced gamma-ray production in the MeV energy range.

    SciTech Connect (OSTI)

    Nelson, R. O. (Ronald O.); Fotiadis, N. (Nikolaos); Devlin, M. J. (Matthew J.); Becker, J. A. (John A.); Garrett, P. E. (Paul E.); Younes, W. (Walid)

    2004-01-01

    Gamma-ray cross section standards for neutron-induced reactions are important in enabling the accurate determination of absolute cross sections from relative measurements of gamma-ray production. In our work we observed a need for improvement in these standards. In particular there are large discrepancies between evaluations of the {sup nat}Fe(n,n{sub 1}'{gamma}) cross section for the 847-keV gamma ray. We have performed (1) absolute cross section measurements, (2) measurements relative to the {sup nat}Cr(n,n{sub 1}'{gamma}) 1434-keV gamma ray, and (3) comparisons using measured total and elastic scattering cross sections to refine our knowledge of the Fe cross section and the closely linked inelastic channel cross section for Fe. Calculation of integral tests of the cross section libraries may indicate that adjustment of the angular distributions of the neutron elastic and inelastic scattering may be needed.

  4. Determination of Thermal Neutron Capture Cross-Sections at Budapest PGAA Facility

    SciTech Connect (OSTI)

    Revay, Zsolt; Belgya, Tamas; Firestone, Richard B.

    2007-10-26

    Prompt gamma activation analysis (PGAA) is a powerful nuclear analytical technique to determine the elemental and isotopic composition of materials. The PGAA facility at Budapest, Hungary is one of the leading laboratories of the world, determining spectroscopic data for chemical analysis to be used in other laboratories. These partial gamma-ray production cross-sections and k{sub 0} values, being proportional to the analytical sensitivities of the chemical elements, can be transformed into thermal neutron capture cross-sections, i.e. the probabilities of the (n,{gamma}) reactions, which are of broader interest in different fields of nuclear physics. Some preliminary results on thermal neutron capture cross-sections are presented.

  5. Empirical Fit to Precision Inclusive Electron-Proton Cross Sections in the Resonance Region

    SciTech Connect (OSTI)

    M.E. Christy; Peter Bosted

    2010-05-01

    An empirical fit is described to measurements of inclusive inelastic electron-proton cross sections in the kinematic range of four-momentum transfer $0 \\le Q^2<8$ GeV$^2$ and final state invariant mass $1.1<3.1$ GeV. The fit is constrained by the recent high precision longitudinal and transverse (L/T) separated cross section measurements from Jefferson Lab Hall C, un-separated Hall C measurements up to $Q^2$ $\\approx 7.5$ ${\\rm GeV}^2$, and photoproduction data at $Q^2 = 0$. Compared to previous fits, the present fit covers a wider kinematic range, fits both transverse and longitudinal cross sections, and features smooth transitions to the photoproduction data at $Q^2=0$ and DIS data at high $Q^2$ and $W$.

  6. PRACTICAL METHOD FOR ESTIMATING NEUTRON CROSS SECTION COVARIANCES IN THE RESONANCE REGION

    SciTech Connect (OSTI)

    Cho, Y.S.; Oblozinsky, P.; Mughabghab,S.F.; Mattoon,C.M.; Herman,M.

    2010-04-30

    Recent evaluations of neutron cross section covariances in the resolved resonance region reveal the need for further research in this area. Major issues include declining uncertainties in multigroup representations and proper treatment of scattering radius uncertainty. To address these issues, the present work introduces a practical method based on kernel approximation using resonance parameter uncertainties from the Atlas of Neutron Resonances. Analytical expressions derived for average cross sections in broader energy bins along with their sensitivities provide transparent tool for determining cross section uncertainties. The role of resonance-resonance and bin-bin correlations is specifically studied. As an example we apply this approach to estimate (n,{gamma}) and (n,el) covariances for the structural material {sup 55}Mn.

  7. First Measurement of Muon Neutrino Charged Current Quasielastic (CCQE) Double Differential Cross Section

    SciTech Connect (OSTI)

    Katori, Teppei; /MIT, LNS

    2009-09-01

    Using a high statistics sample of muon neutrino charged current quasielastic (CCQE) events, we report the first measurement of the double differential cross section (d{sup 2}{sigma}/dT{sub {mu}}d cos {theta}{sub {mu}}) for this process. The result features reduced model dependence and supplies the most complete information on neutrino CCQE scattering to date. Measurements of the absolute cross section as a function of neutrino energy ({sigma}[E{sub v}{sup QE,RFG}]) and the single differential cross section (d{sigma}/dQ{sub QE}{sup 2}) are also provided, largely to facilitate comparison with prior measurements. This data is of particular use for understanding the axial-vector form factor of the nucleon as well as improving the simulation of low energy neutrino interactions on nuclear targets, which is of particular relevance for experiments searching for neutrino oscillations.

  8. Absolute total and partial dissociative cross sections of pyrimidine at electron and proton intermediate impact velocities

    SciTech Connect (OSTI)

    Wolff, Wania Luna, Hugo; Sigaud, Lucas; Montenegro, Eduardo C.; Tavares, Andre C.

    2014-02-14

    Absolute total non-dissociative and partial dissociative cross sections of pyrimidine were measured for electron impact energies ranging from 70 to 400 eV and for proton impact energies from 125 up to 2500 keV. MOs ionization induced by coulomb interaction were studied by measuring both ionization and partial dissociative cross sections through time of flight mass spectrometry and by obtaining the branching ratios for fragment formation via a model calculation based on the Born approximation. The partial yields and the absolute cross sections measured as a function of the energy combined with the model calculation proved to be a useful tool to determine the vacancy population of the valence MOs from which several sets of fragment ions are produced. It was also a key point to distinguish the dissociation regimes induced by both particles. A comparison with previous experimental results is also presented.

  9. Hartree-Fock calculation of the differential photoionization cross sections of small Li clusters

    SciTech Connect (OSTI)

    Galitskiy, S. A.; Artemyev, A. N.; Jänkälä, K.; Lagutin, B. M.; Demekhin, Ph. V.

    2015-01-21

    Cross sections and angular distribution parameters for the single-photon ionization of all electron orbitals of Li{sub 2−8} are systematically computed in a broad interval of the photoelectron kinetic energies for the energetically most stable geometry of each cluster. Calculations of the partial photoelectron continuum waves in clusters are carried out by the single center method within the Hartree-Fock approximation. We study photoionization cross sections per one electron and analyze in some details general trends in the photoionization of inner and outer shells with respect to the size and geometry of a cluster. The present differential cross sections computed for Li{sub 2} are in a good agreement with the available theoretical data, whereas those computed for Li{sub 3−8} clusters can be considered as theoretical predictions.

  10. Code System to Calculate Nuclear Reaction Cross Sections by Evaporation Model.

    Energy Science and Technology Software Center (OSTI)

    2000-11-27

    Version: 00 Both STAPRE and STAPREF are included in this package. STAPRE calculates energy-averaged cross sections for nuclear reactions with emission of particles and gamma rays and fission. The models employed are the evaporation model with inclusion of pre-equilibrium decay and a gamma-ray cascade model. Angular momentum and parity conservation are accounted for. Major improvement in the 1976 STAPRE program relates to level density approach, implemented in subroutine ZSTDE. Generalized superfluid model is incorporated, boltzman-gasmore » modeling of intrinsic state density and semi-empirical modeling of a few-quasiparticle effects in total level density at equilibrium and saddle deformations of actinide nuclei. In addition to the activation cross sections, particle and gamma-ray production spectra are calculated. Isomeric state populations and production cross sections for gamma rays from low excited levels are obtained, too. For fission a single or a double humped barrier may be chosen.« less

  11. Cross sections for electron scattering by propane in the low- and intermediate-energy ranges

    SciTech Connect (OSTI)

    Souza, G. L. C. de; Lee, M.-T.; Sanches, I. P.; Rawat, P.; Iga, I.; Santos, A. S. dos; Machado, L. E.; Sugohara, R. T.; Brescansin, L. M.; Homem, M. G. P.; Lucchese, R. R.

    2010-07-15

    We present a joint theoretical-experimental study on electron scattering by propane (C{sub 3}H{sub 8}) in the low- and intermediate-energy ranges. Calculated elastic differential, integral, and momentum transfer as well as total (elastic + inelastic) and total absorption cross sections are reported for impact energies ranging from 2 to 500 eV. Also, experimental absolute elastic cross sections are reported in the 40- to 500-eV energy range. A complex optical potential is used to represent the electron-molecule interaction dynamics. A theoretical method based on the single-center-expansion close-coupling framework and corrected by the Pade approximant is used to solve the scattering equations. The experimental angular distributions of the scattered electrons are converted to absolute cross sections using the relative flow technique. The comparison of our calculated with our measured results, as well as with other experimental and theoretical data available in the literature, is encouraging.

  12. Measurements of neutron capture cross section for {sup 207,208}Pb

    SciTech Connect (OSTI)

    Segawa, M.; Toh, Y.; Harada, H.; Kitatani, F.; Koizumi, M.; Fukahori, T.; Iwamoto, N.; Iwamoto, O.; Oshima, M.; Hatsukawa, Y.; Nagai, Y.; Igashira, M.; Kamada, S.; Tajika, M.

    2014-05-02

    The neutron capture cross sections for {sup 207,208}Pb have been measured in the neutron energy region from 10 to 110 keV. The ?-rays cascaded from a capture state to the ground state or low-lying states of {sup 208,209}Pb were observed for the first time, using an anti-Compton Nal(Tl) spectrometer and a TOF method. The observed discrete ?-ray energy spectra enabled us to determine neutron capture cross sections for {sup 207,208}Pb with small systematic errors, since we could distinguish ?-ray of {sup 207,208}Pb(n,?) reactions from background ?-ray with use of the ?-ray spectra. The obtained cross sections include both contributions of resonance and direct capture components different from the previous TOF measurements.

  13. Measurement of the neutron capture cross section of {sup 15}N J

    SciTech Connect (OSTI)

    MeiBner, N.J.; Schatz, H.; Herndl, H.; Wiescher, M.

    1995-10-01

    Neutron capture reactions on fight nuclei may be of considerable importance for the s-process nucleosynthesis in red giant stars as well as in inhomogeneous big bang scenarios and high entropy supernovae neutrino bubbles. To determine the reaction rates for such different temperature conditions, the cross sections need to be known for a wide energy range. The reaction {sup 15}N(n,{gamma}) represents an important link in the reaction seququences for the production of heavier isotopes in such scenarios. At high temperature conditions, the cross section is not only influenced by a non resonant a-wave contribution but also by a non resonant p-wave contribution and higher energy resonances. The (n,{gamma}) cross section has been measured at the Forschungszentrum Karlsruhe for different neutron energies using a fast cyclic neutron activation technique. The technique and the results will be presented.

  14. Measurement of the scattering cross section of slow neutrons on liquid parahydrogen from neutron transmission

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

    Grammer, K. B.; Alarcon, R.; Barrón-Palos, L.; Blyth, D.; Bowman, J. D.; Calarco, J.; Crawford, C.; Craycraft, K.; Evans, D.; Fomin, N.; et al

    2015-05-08

    Liquid hydrogen is a dense Bose fluid whose equilibrium properties are both calculable from first principles using various theoretical approaches and of interest for the understanding of a wide range of questions in many-body physics. Unfortunately, the pair correlation function g(r) inferred from neutron scattering measurements of the differential cross section dσ/dΩ from different measurements reported in the literature are inconsistent. We have measured the energy dependence of the total cross section and the scattering cross section for slow neutrons with energies between 0.43 and 16.1 meV on liquid hydrogen at 15.6 K (which is dominated by the parahydrogen component)more » using neutron transmission measurements on the hydrogen target of the NPDGamma collaboration at the Spallation Neutron Source at Oak Ridge National Laboratory. The relationship between the neutron transmission measurement we perform and the total cross section is unambiguous, and the energy range accesses length scales where the pair correlation function is rapidly varying. At 1 meV our measurement is a factor of 3 below the data from previous work. We present evidence that these previous measurements of the hydrogen cross section, which assumed that the equilibrium value for the ratio of orthohydrogen and parahydrogen has been reached in the target liquid, were in fact contaminated with an extra nonequilibrium component of orthohydrogen. Liquid parahydrogen is also a widely used neutron moderator medium, and an accurate knowledge of its slow neutron cross section is essential for the design and optimization of intense slow neutron sources. Furthermore, we describe our measurements and compare them with previous work.« less

  15. Measurement of the scattering cross section of slow neutrons on liquid parahydrogen from neutron transmission

    SciTech Connect (OSTI)

    Grammer, K. B.; Alarcon, R.; Barrón-Palos, L.; Blyth, D.; Bowman, J. D.; Calarco, J.; Crawford, C.; Craycraft, K.; Evans, D.; Fomin, N.; Fry, J.; Gericke, M.; Gillis, R. C.; Greene, G. L.; Hamblen, J.; Hayes, C.; Kucuker, S.; Mahurin, R.; Maldonado-Velázquez, M.; Martin, E.; McCrea, M.; Mueller, P. E.; Musgrave, M.; Nann, H.; Penttilä, S. I.; Snow, W. M.; Tang, Z.; Wilburn, W. S.

    2015-05-08

    Liquid hydrogen is a dense Bose fluid whose equilibrium properties are both calculable from first principles using various theoretical approaches and of interest for the understanding of a wide range of questions in many-body physics. Unfortunately, the pair correlation function g(r) inferred from neutron scattering measurements of the differential cross section dσ/dΩ from different measurements reported in the literature are inconsistent. We have measured the energy dependence of the total cross section and the scattering cross section for slow neutrons with energies between 0.43 and 16.1 meV on liquid hydrogen at 15.6 K (which is dominated by the parahydrogen component) using neutron transmission measurements on the hydrogen target of the NPDGamma collaboration at the Spallation Neutron Source at Oak Ridge National Laboratory. The relationship between the neutron transmission measurement we perform and the total cross section is unambiguous, and the energy range accesses length scales where the pair correlation function is rapidly varying. At 1 meV our measurement is a factor of 3 below the data from previous work. We present evidence that these previous measurements of the hydrogen cross section, which assumed that the equilibrium value for the ratio of orthohydrogen and parahydrogen has been reached in the target liquid, were in fact contaminated with an extra nonequilibrium component of orthohydrogen. Liquid parahydrogen is also a widely used neutron moderator medium, and an accurate knowledge of its slow neutron cross section is essential for the design and optimization of intense slow neutron sources. Furthermore, we describe our measurements and compare them with previous work.

  16. Optimization of multi-group cross sections for fast reactor analysis

    SciTech Connect (OSTI)

    Chin, M. R.; Manalo, K. L.; Edgar, C. A.; Paul, J. N.; Molinar, M. P.; Redd, E. M.; Yi, C.; Sjoden, G. E.

    2013-07-01

    The selection of the number of broad energy groups, collapsed broad energy group boundaries, and their associated evaluation into collapsed macroscopic cross sections from a general 238-group ENDF/B-VII library dramatically impacted the k eigenvalue for fast reactor analysis. An analysis was undertaken to assess the minimum number of energy groups that would preserve problem physics; this involved studies using the 3D deterministic transport parallel code PENTRAN, the 2D deterministic transport code SCALE6.1, the Monte Carlo based MCNP5 code, and the YGROUP cross section collapsing tool on a spatially discretized MOX fuel pin comprised of 21% PUO{sub 2}-UO{sub 2} with sodium coolant. The various cases resulted in a few hundred pcm difference between cross section libraries that included the 238 multi-group reference, and cross sections rendered using various reaction and adjoint weighted cross sections rendered by the YGROUP tool, and a reference continuous energy MCNP case. Particular emphasis was placed on the higher energies characteristic of fission neutrons in a fast spectrum; adjoint computations were performed to determine the average per-group adjoint fission importance for the MOX fuel pin. This study concluded that at least 10 energy groups for neutron transport calculations are required to accurately predict the eigenvalue for a fast reactor system to within 250 pcm of the 238 group case. In addition, the cross section collapsing/weighting schemes within YGROUP that provided a collapsed library rendering eigenvalues closest to the reference were the contribution collapsed, reaction rate weighted scheme. A brief analysis on homogenization of the MOX fuel pin is also provided, although more work is in progress in this area. (authors)

  17. POINT 2011: ENDF/B-VII.1 Beta2 Temperature Dependent Cross Section Library

    SciTech Connect (OSTI)

    Cullen, D E

    2011-04-07

    This report is one in the series of 'POINT' reports that over the years have presented temperature dependent cross sections for the then current version of ENDF/B. In each case I have used my personal computer at home and publicly available data and codes. I have used these in combination to produce the temperature dependent cross sections used in applications and presented in this report. I should mention that today anyone with a personal computer can produce these results. The latest ENDF/B-VII.1 beta2 data library was recently and is now freely available through the National Nuclear Data Center (NNDC), Brookhaven National Laboratory. This release completely supersedes all preceding releases of ENDF/B. As distributed the ENDF/B-VII.1 data includes cross sections represented in the form of a combination of resonance parameters and/or tabulated energy dependent cross sections, nominally at 0 Kelvin temperature. For use in our applications the ENDF/B-VII.1 library has been processed into cross sections at eight neutron reactor like temperatures, between 0 and 2100 Kelvin, in steps of 300 Kelvin (the exception being 293.6 Kelvin, for exact room temperature at 20 Celsius). It has also been processed to five astrophysics like temperatures, 1, 10, 100 eV, 1 and 10 keV. For reference purposes, 300 Kelvin is approximately 1/40 eV, so that 1 eV is approximately 12,000 Kelvin. At each temperature the cross sections are tabulated and linearly interpolable in energy. All results are in the computer independent ENDF-6 character format [R2], which allows the data to be easily transported between computers. In its processed form the POINT 2011 library is approximately 16 gigabyte in size and is distributed on one compressed DVDs (see, below for the details of the contents of each DVD).

  18. Measurement of the scattering cross section of slow neutrons on liquid parahydrogen from neutron transmission

    SciTech Connect (OSTI)

    Grammer, K. B.; Alarcon, R.; Barrn-Palos, L.; Blyth, D.; Bowman, J. D.; Calarco, J.; Crawford, C.; Craycraft, K.; Evans, D.; Fomin, N.; Fry, J.; Gericke, M.; Gillis, R. C.; Greene, G. L.; Hamblen, J.; Hayes, C.; Kucuker, S.; Mahurin, R.; Maldonado-Velzquez, M.; Martin, E.; McCrea, M.; Mueller, P. E.; Musgrave, M.; Nann, H.; Penttil, S. I.; Snow, W. M.; Tang, Z.; Wilburn, W. S.

    2015-05-08

    Liquid hydrogen is a dense Bose fluid whose equilibrium properties are both calculable from first principles using various theoretical approaches and of interest for the understanding of a wide range of questions in many-body physics. Unfortunately, the pair correlation function g(r) inferred from neutron scattering measurements of the differential cross section d?/d? from different measurements reported in the literature are inconsistent. We have measured the energy dependence of the total cross section and the scattering cross section for slow neutrons with energies between 0.43 and 16.1 meV on liquid hydrogen at 15.6 K (which is dominated by the parahydrogen component) using neutron transmission measurements on the hydrogen target of the NPDGamma collaboration at the Spallation Neutron Source at Oak Ridge National Laboratory. The relationship between the neutron transmission measurement we perform and the total cross section is unambiguous, and the energy range accesses length scales where the pair correlation function is rapidly varying. At 1 meV our measurement is a factor of 3 below the data from previous work. We present evidence that these previous measurements of the hydrogen cross section, which assumed that the equilibrium value for the ratio of orthohydrogen and parahydrogen has been reached in the target liquid, were in fact contaminated with an extra nonequilibrium component of orthohydrogen. Liquid parahydrogen is also a widely used neutron moderator medium, and an accurate knowledge of its slow neutron cross section is essential for the design and optimization of intense slow neutron sources. Furthermore, we describe our measurements and compare them with previous work.

  19. MiniBooNE Anti-Neutrino CCQE Cross Section Data Release

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

    Anti-Neutrino Double-Differential Charged Current Quasi-Elastic Cross Section", arXiv:1301.7067 [hep-ex] The following MiniBooNE information from the anti-neutrino CCQE cross section paper is made available to the public: νμ CCQE data: MiniBooNE flux table of MiniBooNE anti-neutrino mode flux by neutrino species (Figure 1 and Tables XI-XII). Note that, based on the constraints of the in situ measurements, the muon neutrino flux spectrum given here should be scaled by 0.77. flux-integrated

  20. Solar fusion cross sections II: the pp chain and CNO cycles

    SciTech Connect (OSTI)

    Adelberger, E G; Bemmerer, D; Bertulani, C A; Chen, J -W; Costantini, H; Couder, M; Cyburt, R; Davids, B; Freedman, S J; Gai, M; Garcia, A; Gazit, D; Gialanella, L; Greife, U; Hass, M; Heeger, K; Haxton, W C; Imbriani, G; Itahashi, T; Junghans, A; Kubodera, K; Langanke, K; Leitner, D; Leitner, M; Marcucci, L E; Motobayashi, T; Mukhamedzhanov, A; Nollett, Kenneth M; Nunes, F M; Park, T -S; Parker, P D; Prati, P; Ramsey-Musolf, M J; Hamish Robertson, R G; Schiavilla, R; Simpson, E C; Snover, K A; Spitaleri, C; Strieder, F; Suemmerer, K; Trautvetter, R E; Tribble, R E; Typel, S; Uberseder, E; Vetter, P; Wiescher, M

    2011-04-01

    The available data on nuclear fusion cross sections important to energy generation in the Sun and other hydrogen-burning stars and to solar neutrino production are summarized and critically evaluated. Recommended values and uncertainties are provided for key cross sections, and a recommended spectrum is given for 8B solar neutrinos. Opportunities for further increasing the precision of key rates are also discussed, including new facilities, new experimental techniques, and improvements in theory. This review, which summarizes the conclusions of a workshop held at the Institute for Nuclear Theory, Seattle, in January 2009, is intended as a 10-year update and supplement to 1998, Rev. Mod. Phys. 70, 1265.

  1. Calculation of the extinction cross section and lifetime of a gold nanoparticle using FDTD simulations

    SciTech Connect (OSTI)

    Radhakrishnan, Archana; Murugesan, Dr V.

    2014-10-15

    The electromagnetic theory of light explains the behavior of light in most of the domains quite accurately. The problem arises when the exact solution of the Maxwell's equation is not present, in case of objects with arbitrary geometry. To find the extinction cross-section and lifetime of the gold nanoparticle, the software FDTD solutions 8.6 by Lumerical is employed. The extinction cross-sections and lifetimes of Gold nanospheres of different sizes and arrangements are studied using pulse lengths of the order of femtoseconds. The decay constant and other properties are compared. Further, the lifetimes are calculated using frequency and time domain calculations.

  2. Measurements of the breakup and neutron removal cross sections for {sup 16}C

    SciTech Connect (OSTI)

    Ashwood, N. I.; Freer, M.; Clarke, N.M.; Curtis, N.; Soic, N.; Ziman, V.A.; Angelique, J.C.; Lecouey, J.L.; Marques, F.M.; Normand, G.; Orr, N.A.; Timis, C.; Bouchat, V.; Hanappe, F.; Kerckx, Y.; Materna, T.; Catford, W.N.; Dorvaux, O.; Stuttge, L.

    2004-12-01

    Measurements of the breakup and the neutron removal reactions of {sup 16}C have been made at 46 MeV/A and the decay cross sections measured. A correlation between the cluster breakup channels and the reaction Q value suggests that the reaction mechanism is strongly linked to quasielastic processes. No enhancement of the two-body cluster breakup cross section is seen for {sup 16}C. This result would indicate that {sup 16}C does not have a well developed cluster structure in the ground state, in agreement with recent calculations.

  3. Neutron capture cross sections of {sup 148}Gd and the decay of {sup 149}Gd

    SciTech Connect (OSTI)

    Rios, M. G.; Casperson, R. J.; Krane, K. S.; Norman, E. B.

    2006-10-15

    The thermal cross section and resonance integral were measured for radiative neutron capture by radioactive {sup 148}Gd. The deduced values are {sigma}=9600{+-}900 b and I=28,200{+-}2300. We also deduced upper limits for the n,p and n, {alpha} cross sections, respectively, 0.25 b and 13 b. The {gamma}-ray spectrum from the decay of {sup 149}Gd was studied in singles mode at high resolution to verify the previously determined energies and intensities. From the latter measurements, new transitions are proposed and upper limits are deduced for previously reported transitions.

  4. Geologic Map and Cross Sections of the McGinness Hills Geothermal Area - GIS Data

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

    Faulds, James E.

    2013-12-31

    Geologic map data in shapefile format that includes faults, unit contacts, unit polygons, attitudes of strata and faults, and surficial geothermal features. 5 cross?sections in Adobe Illustrator format. Comprehensive catalogue of drill?hole data in spreadsheet, shapefile, and Geosoft database formats. Includes XYZ locations of well heads, year drilled, type of well, operator, total depths, well path data (deviations), lithology logs, and temperature data. 3D model constructed with EarthVision using geologic map data, cross?sections, drill?hole data, and geophysics.

  5. e+ e- to Hadrons Cross-Sections at BaBar

    SciTech Connect (OSTI)

    Muller, David; /SLAC

    2011-11-30

    We present an overview of cross-section measurements at BABAR. In e{sup {+-}} {yields} few-body processes at a center-of-mass energy E{sub CM} = 10.6 GeV we make new QCD tests and the first observation of two-virtual-photon annihilations into hadrons. Studies at lower {radical}s, using radiative return, yield new/improved data on spectroscopy, form factors and the total hadronic cross section, an important input to calculations of g{sub {mu}}-2 and {alpha}(M{sub Z}). We also present an inclusive measurement of the running of {alpha}.

  6. Code System to Create Broad-Group Cross Sections with Resonance Interference and Self-Shielding from Fine-Group and Pointwise Cross Sections.

    Energy Science and Technology Software Center (OSTI)

    2007-10-31

    Version: 02 RSICC received MICROX‑2 through the NEADB (identifier is NEA‑1562/02.) This is an improved version of the original MICROX-2 two-region spectrum code, which was developed at General Atomic, to prepare broad group neutron cross sections for use in diffusion-and/or transport theory codes from an input library of fine group and pointwise cross sections. The MICROX-2 code can explicitly account for the overlap and interference effects between resonances in both the resonance and thermal neutronmore » energy ranges and allows the simulta?neous treatment of leakage and resonance self-shielding in doubly heterogeneous lattice cells. MICROR runs as a module of NJOY 89.62; the NJOY calling module is included in the package. This release has been changed in that the MODER module from NJOY 94.0, too, has been included as subprogramm of NJOY 89.62, so as to make the code system completely selfconsistent, i.e. without requiring the use of some NJOY version to convert pendf and gendf from coded to binary. Using data from pointwise and groupwise NJOY tapes, the stand-alone MICROR reformatting program produces files containing basic nuclear data to be used by MICROX-2. MICROR edits PENDF and GENDF data files from NJOY to create FDTAP?E, GGTA?PE and GARTA?PE input files for MICROX-2. NJOY is not included in this package. Some data libraries are included for example cases; these data were generated from data in 193 groups as well as from point-wise cross sections from NJOY (Edition 89.62).« less

  7. ENDF/B-VII.1 Final Temperature Dependent Cross Section Library.

    Energy Science and Technology Software Center (OSTI)

    2012-03-03

    Version 00 For use in applications the ENDF/B-VII.1 library has been processed into the form of temperature dependent cross sections at eight neutron reactor like temperatures, between 0 K and 2100 K, in steps of 300 K (the exception being 293.6 K, for exact room temperature at 20 Celsius). It has also been processed to five astrophysics like temperatures—1, 10, and 100 eV; and 1 and 10 keV. For reference purposes, 300 K is approximatelymore » 1/40 eV, so that 1 eV is approximately 12,000 K. At each temperature the cross sections are tabulated and linearly interpolable in energy. As distributed the original evaluated data includes cross sections represented in the form of a combination of resonance parameters and/or tabulated energy dependent cross sections, nominally at 0 K. For use in applications, this data has been processed using the 2012 version of the ENDF/B pre-processing codes PREPRO 2012 to produce temperature dependent, linearly interpolable in energy, tabulated cross sections, in the ENDF-6 format. The steps required and codes used to produce room temperature, linearly interpolable tabulated cross sections, in the ENDF-6 format, are described below; the name of each code in given in parenthesis; for details of each code see reference. Here are the steps, and PREPRO 2012 codes, used to process the data, in the order in which the codes were used. 1) Linearly interpolable, tabulated cross sections (LINEAR) 2) Including the resonance contribution (RECENT) 3) Doppler broaden all cross sections to temperature (SIGMA1) 4) Check data, define redundant cross sections by summation (FIXUP) 5) Update evaluation dictionary in MF/MT=1/451 (DICTIN) For the "cold" (0 K) data steps 1), 2) and 4), 5) were used (no Doppler broadening). For the data at other temperatures, after steps 1) and 2), the data was Doppler broadened to each temperature using step 3), and the results were then made consistent with the ENDF/B formats and conventions using steps 4) and 5), to

  8. Dynamic interaction potential and the scattering cross sections of the semiclassical plasma particles

    SciTech Connect (OSTI)

    Dzhumagulova, K. N.; Shalenov, E. O.; Gabdullina, G. L.

    2013-04-15

    The dynamic model of the charged particles interaction in non-ideal semiclassical plasma is presented. This model takes into account the quantum mechanical diffraction effect and the dynamic screening effect. On the basis of the dynamic interaction potential, the electron scattering cross sections are investigated. Comparison with the results obtained on the basis of other models and conclusions were made.

  9. Status of the top quark: Top production cross section and top properties

    SciTech Connect (OSTI)

    Boisvert, V.; /Rochester U.

    2006-08-01

    This report describes the latest cross section and property measurements associated with the top quark at the Tevatron Run II. The largest data sample used is 760 pb{sup -1} of integrated luminosity. Due to its large mass, the top quark might be involved in the process of electroweak symmetry breaking, making it a useful probe for signs of new physics.

  10. A Code to Produce Cell Averaged Cross Sections for Fast Critical Assemblies and Fast Power Reactors.

    Energy Science and Technology Software Center (OSTI)

    1987-05-14

    Version 00 SLAROM solves the neutron integral transport equations to determine the flux distribution and spectra in a fast reactor lattice and calculates cell averaged effective cross sections. The code uses multigroup data of the type in DLC-111/JFS that use Bondarenko factors for resonance effects.

  11. 70 Group Neutron Fast Reactor Cross Section Set Based on JENDL-2B.

    Energy Science and Technology Software Center (OSTI)

    1984-02-06

    Version 00 These multigroup cross sections are used in fast reactor calculations. The benchmark calculations for the 23 fast critical assemblies used in the benchmark tests of JFS-2 were performed with one-dimensional diffusion theory by using the JFS-3-J2 set.

  12. 137 and 26 Neutron Multigroup Cross Section Library with the Bondarenko Type Shielding Table.

    Energy Science and Technology Software Center (OSTI)

    1986-02-16

    Version 00 The basic function of MGCLIB is to generate effective neutron cross section sets in either 137 or 26 group structures for use in the discrete ordinates codes ANISN-JR or DOT 3.5 or in the Monte Carlo codes KENO-IV or MULTI-KENO.

  13. Photodissociation in quantum chaotic systems: Random-matrix theory of cross-section fluctuations

    SciTech Connect (OSTI)

    Fyodorov, Y.V. [Fachbereich Physik, Universitaet-GH Essen, D-45117 Essen (Germany)] [Fachbereich Physik, Universitaet-GH Essen, D-45117 Essen (Germany); Alhassid, Y. [Center for Theoretical Physics, Sloane Physics Laboratory, Yale University, New Haven, Connecticut 06520 (United States)] [Center for Theoretical Physics, Sloane Physics Laboratory, Yale University, New Haven, Connecticut 06520 (United States)

    1998-11-01

    Using the random matrix description of open quantum chaotic systems we calculate in closed form the universal autocorrelation function and the probability distribution of the total photodissociation cross section in the regime of quantum chaos. {copyright} {ital 1998} {ital The American Physical Society}

  14. Differential cross section for coherent photon scattering from /sup 4/He at 180 MeV

    SciTech Connect (OSTI)

    Austin, E.J.; Booth, E.C.; McIntyre, E.K.; Miller, J.P.; Roberts, B.L.; Whitehouse, D.A.; Dodson, G.

    1986-08-25

    We report the measurement of the differential scattering cross section for coherent photon scattering (nuclear Compton scattering) from /sup 4/He at an average energy of 180 MeV. This represents the first direct observation of the coherent process on a complex nucleus above the pion threshold. The results are compared with the predicton of a claculation utilizing the isobar-hole formalism.

  15. Absolute measurement of the 242Pu neutron-capture cross section

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

    Buckner, M. Q.; Wu, C. Y.; Henderson, R. A.; Bucher, B.; Chyzh, A.; Bredeweg, T. A.; Baramsai, B.; Couture, A.; Jandel, M.; Mosby, S.; et al

    2016-04-21

    Here, the absolute neutron-capture cross section of 242Pu was measured at the Los Alamos Neutron Science Center using the Detector for Advanced Neutron-Capture Experiments array along with a compact parallel-plate avalanche counter for fission-fragment detection. The first direct measurement of the 242Pu(n,γ) cross section was made over the incident neutron energy range from thermal to ≈ 6 keV, and the absolute scale of the (n,γ) cross section was set according to the known 239Pu(n,f) resonance at En,R = 7.83 eV. This was accomplished by adding a small quantity of 239Pu to the 242Pu sample. The relative scale of the crossmore » section, with a range of four orders of magnitude, was determined for incident neutron energies from thermal to ≈ 40 keV. Our data, in general, are in agreement with previous measurements and those reported in ENDF/B-VII.1; the 242Pu(n,γ) cross section at the En,R = 2.68 eV resonance is within 2.4% of the evaluated value. However, discrepancies exist at higher energies; our data are ≈30% lower than the evaluated data at En ≈ 1 keV and are approximately 2σ away from the previous measurement at En ≈ 20 keV.« less

  16. Total cross sections for positron scattering from benzene, cyclohexane, and aniline

    SciTech Connect (OSTI)

    Zecca, Antonio; Moser, Norberto; Perazzolli, Chiara; Salemi, Alessandro; Brunger, Michael J.

    2007-08-15

    We use a linear transmission technique to measure total cross sections for positron scattering from benzene, cyclohexane, and aniline. In the case of cyclohexane, the energy range of the present study is 0.1-20 eV, while for benzene and aniline it is 0.2-20 eV. With respect to benzene and cyclohexane, comparison is made to the only other existing results we know of [Makochekanwa and co-workers, Phys. Rev. A 68, 032707 (2003); 72, 042705 (2005)]. Agreement with those data is only marginal, being particularly poor at the overlap lower energies. Unlike Kimura et al. [J. Phys. B 37, 1461 (2004)], we find the low-energy dependence of the positron-benzene total cross sections to be qualitatively similar to those found in the electron channel [Gulley et al., J. Phys. B 31, 2735 (1998)]. We believe that the present positron-aniline total cross sections represent the first time such data have been measured. These cross sections are almost identical to those we found for benzene, suggesting that substitution of hydrogen by the amine group on the aromatic ring is largely irrelevant to the scattering process in the energy regimes considered.

  17. Systematics of (n,2n) and (n,3n) Cross Sections.

    Energy Science and Technology Software Center (OSTI)

    1991-10-08

    Version 00 SC2N3N can be used to calculate the (n2n) and (n3n) cross section in the energy region from threshold to about 25 MeV with the systematics parameters which well reproduce the experiment in the mass region of 23.le.A.le.238 (especially between 45 and 197.)

  18. BOXER: Fine-flux Cross Section Condensation, 2D Few Group Diffusion and Transport Burnup Calculations

    Energy Science and Technology Software Center (OSTI)

    2010-02-01

    Neutron transport, calculation of multiplication factor and neutron fluxes in 2-D configurations: cell calculations, 2-D diffusion and transport, and burnup. Preparation of a cross section library for the code BOXER from a basic library in ENDF/B format (ETOBOX).

  19. Measuring Cross-Section and Estimating Uncertainties with the fissionTPC

    SciTech Connect (OSTI)

    Bowden, N.; Manning, B.; Sangiorgio, S.; Seilhan, B.

    2015-01-30

    The purpose of this document is to outline the prescription for measuring fission cross-sections with the NIFFTE fissionTPC and estimating the associated uncertainties. As such it will serve as a work planning guide for NIFFTE collaboration members and facilitate clear communication of the procedures used to the broader community.

  20. Cross section analyses in MiniBooNE and SciBooNE experiments

    SciTech Connect (OSTI)

    Katori, Teppei

    2015-05-15

    The MiniBooNE experiment (2002-2012) and the SciBooNE experiment (2007-2008) are modern high statistics neutrino experiments, and they developed many new ideas in neutrino cross section analyses. In this note, I discuss selected topics of these analyses.

  1. Measurement of muon neutrino and antineutrino induced single neutral pion production cross sections

    SciTech Connect (OSTI)

    Anderson, Colin E.

    2011-05-01

    Elucidating the nature of neutrino oscillation continues to be a goal in the vanguard of the efforts of physics experiment. As neutrino oscillation searches seek an increasingly elusive signal, a thorough understanding of the possible backgrounds becomes ever more important. Measurements of neutrino-nucleus interaction cross sections are key to this understanding. Searches for νμ → νe oscillation - a channel that may yield insight into the vanishingly small mixing parameter θ13, CP violation, and the neutrino mass hierarchy - are particularly susceptible to contamination from neutral current single π0 (NC 1π0) production. Unfortunately, the available data concerning NC 1π0 production are limited in scope and statistics. Without satisfactory constraints, theoretical models of NC 1π0 production yield substantially differing predictions in the critical Eν ~ 1 GeV regime. Additional investigation of this interaction can ameliorate the current deficiencies. The Mini Booster Neutrino Experiment (MiniBooNE) is a short-baseline neutrino oscillation search operating at the Fermi National Accelerator Laboratory (Fermilab). While the oscillation search is the principal charge of the MiniBooNE collaboration, the extensive data (~ 106 neutrino events) offer a rich resource with which to conduct neutrino cross section measurements. This work concerns the measurement of both neutrino and antineutrino NC 1π0 production cross sections at MiniBooNE. The size of the event samples used in the analysis exceeds that of all other similar experiments combined by an order of magnitude. We present the first measurements of the absolute NC 1π0 cross section as well as the first differential cross sections in both neutrino and antineutrino mode. Specifically, we measure single differential cross sections with respect to pion momentum and pion angle. We find the

  2. SENSIT: a cross-section and design sensitivity and uncertainty analysis code. [In FORTRAN for CDC-7600, IBM 360

    SciTech Connect (OSTI)

    Gerstl, S.A.W.

    1980-01-01

    SENSIT computes the sensitivity and uncertainty of a calculated integral response (such as a dose rate) due to input cross sections and their uncertainties. Sensitivity profiles are computed for neutron and gamma-ray reaction cross sections of standard multigroup cross section sets and for secondary energy distributions (SEDs) of multigroup scattering matrices. In the design sensitivity mode, SENSIT computes changes in an integral response due to design changes and gives the appropriate sensitivity coefficients. Cross section uncertainty analyses are performed for three types of input data uncertainties: cross-section covariance matrices for pairs of multigroup reaction cross sections, spectral shape uncertainty parameters for secondary energy distributions (integral SED uncertainties), and covariance matrices for energy-dependent response functions. For all three types of data uncertainties SENSIT computes the resulting variance and estimated standard deviation in an integral response of interest, on the basis of generalized perturbation theory. SENSIT attempts to be more comprehensive than earlier sensitivity analysis codes, such as SWANLAKE.

  3. Solid oxide fuel cell with transitioned cross-section for improved anode gas management at the open end

    DOE Patents [OSTI]

    Zafred, Paolo R.; Draper, Robert

    2012-01-17

    A solid oxide fuel cell (400) is made having a tubular, elongated, hollow, active section (445) which has a cross-section containing an air electrode (452) a fuel electrode (454) and solid oxide electrolyte (456) between them, where the fuel cell transitions into at least one inactive section (460) with a flattened parallel sided cross-section (462, 468) each cross-section having channels (472, 474, 476) in them which smoothly communicate with each other at an interface section (458).

  4. Exciton Model Code System for Calculating Preequilibrium and Direct Double Differential Cross Sections.

    Energy Science and Technology Software Center (OSTI)

    2007-07-09

    Version 02 PRECO-2006 is a two-component exciton model code for the calculation of double differential cross sections of light particle nuclear reactions. PRECO calculates the emission of light particles (A = 1 to 4) from nuclear reactions induced by light particles on a wide variety of target nuclei. Their distribution in both energy and angle is calculated. Since it currently only considers the emission of up to two particles in any given reaction, it ismore » most useful for incident energies of 14 to 30 MeV when used as a stand-alone code. However, the preequilibrium calculations are valid up to at least around 100 MeV, and these can be used as input for more complete evaporation calculations, such as are performed in a Hauser-Feshbach model code. Finally, the production cross sections for specific product nuclides can be obtained« less

  5. Absolute differential cross sections for elastic scattering of electrons from pyrimidine

    SciTech Connect (OSTI)

    Maljkovic, J. B.; Milosavljevic, A. R.; Sevic, D.; Marinkovic, B. P.; Blanco, F.

    2009-05-15

    Differential cross sections (DCSs) for elastic scattering of electrons from pyrimidine (C{sub 4}H{sub 4}N{sub 2}) are presented for incident energies from 50 to 300 eV. The measurements were performed using a cross beam technique, for scattering angles from 20 deg. to 110 deg. The relative DCSs were measured as a function of both the angle and incident energy and the absolute DCSs were determined using the relative flow method. The calculations of electron interaction cross sections are based on a corrected form of the independent-atom method, known as the screen corrected additivity rule procedure and using an improved quasifree absorption model. Calculated results agree very well with the experiment.

  6. An Algorithm for Decomposition of the Charged Particle Scattering Cross Sections into Singular and Regular Components

    SciTech Connect (OSTI)

    Inanc, Feyzi

    2005-04-09

    Any radiography simulation effort that involves high energy photons should also address charged particle transport problem as well. The scattering cross sections with the charged particles, namely electrons and positrons, go through elastic and inelastic scattering interactions that are highly anisotropic. The conventional Boltzmann operator used in the transport computations can not represent the highly anisotropic scattering interactions. One way is to implement Fokker-Planck operators. The implementation of Fokker-Planck operators requires decomposition of scattering kernels into singular and regular components. This paper introduces an algorithm on how to decompose the elastic and inelastic scattering cross sections into singular and regular components and how to compute momentum transfer and stopping power coefficients from singular components.

  7. Measurement of the absolute differential cross section of proton–proton elastic scattering at small angles

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

    Mchedlishvili, D.; Chiladze, D.; Dymov, S.; Bagdasarian, Z.; Barsov, S.; Gebel, R.; Gou, B.; Hartmann, M.; Kacharava, A.; Keshelashvili, I.; et al

    2016-02-03

    The differential cross section for proton-proton elastic scattering has been measured at a beam kinetic energy of 1.0 GeV and in 200 MeV steps from 1.6 to 2.8 GeV for centre-of-mass angles in the range from 12°-16° to 25°-30°, depending on the energy. A precision in the overall normalisation of typically 3% was achieved by studying the energy losses of the circulating beam of the COSY storage ring as it passed repeatedly through the windowless hydrogen target of the ANKE magnetic spectrometer. It is shown that the data have a significant impact upon the results of a partial wave analysis.more » Furthermore, after extrapolating the differential cross sections to the forward direction, the results are broadly compatible with the predictions of forward dispersion relations.« less

  8. Symmetric charge-transfer cross sections of IIIa rare-earth-metal elements

    SciTech Connect (OSTI)

    Hashida, Masaki; Sakabe, Shuji; Izawa, Yasukazu

    2011-03-15

    Symmetric charge-transfer cross sections of IIIa rare-earth-metal elements (Sc, Y, and Gd) in the impact energy range of 30 to 1000 eV were measured for the first time. The experiments were performed with a crossed-beam apparatus that featured primary ion production by photoionization with a tunable dye laser. Comparing the cross sections of IIIa rare-earth-metal elements ({sigma}{sub Sc}, {sigma}{sub Y}, and {sigma}{sub Gd}) with those of alkali metals or helium {sigma}{sub 0}, we found that {sigma}{sub 0{approx_equal}{sigma}Sc}<{sigma}{sub Y}<{sigma}{sub Gd{approx_equal}}2{sigma}{sub 0}at an impact energy of 1000 eV.

  9. Cross sections calculated for cold fusion reactions for producing superheavy nuclei

    SciTech Connect (OSTI)

    Smolanczuk, Robert

    2008-08-15

    We propose a handy formula for calculating the formation cross sections for optimal bombarding energies for transactinides (superheavy elements). By means of the proposed formula the cross sections for asymmetric and symmetric cold fusion reactions (one-neutron-out reactions) are calculated. The fusion barrier and its position are calculated by using the folding heavy-ion potential that for spherical reaction partners has the form of a seventh-order polynomial of the radial coordinate with built-in dependence on the thickness of the nuclear surface, as well as on the separation energy of the least bound nucleon. Possibilities of further experimental exploitation of cold fusion in producing the superheavy nuclei are briefly discussed.

  10. Design and optimization of a harmonic probe with step cross section in multifrequency atomic force microscopy

    SciTech Connect (OSTI)

    Cai, Jiandong; Zhang, Li; Wang, Michael Yu

    2015-12-15

    In multifrequency atomic force microscopy (AFM), probe’s characteristic of assigning resonance frequencies to integer harmonics results in a remarkable improvement of detection sensitivity at specific harmonic components. The selection criterion of harmonic order is based on its amplitude’s sensitivity on material properties, e.g., elasticity. Previous studies on designing harmonic probe are unable to provide a large design capability along with maintaining the structural integrity. Herein, we propose a harmonic probe with step cross section, in which it has variable width in top and bottom steps, while the middle step in cross section is kept constant. Higher order resonance frequencies are tailored to be integer times of fundamental resonance frequency. The probe design is implemented within a structural optimization framework. The optimally designed probe is micromachined using focused ion beam milling technique, and then measured with an AFM. The measurement results agree well with our resonance frequency assignment requirement.

  11. Cross section sensitivity study for U. S. Fusion Engineering Device (FED)

    SciTech Connect (OSTI)

    Pelloni, S.; Cheng, E.T.

    1983-09-01

    The U.S. Fusion Engineering Device (FED) was used as a basis to investigate the uncertainties of several neutronics performance parameters that arise due to nuclear data uncertainties. The neutron flux distribution was calculated using the discrete-ordinates transport code ANISN. Nuclear data considered were from the VITAMIN-C (DLC-41) library. Atomic displacement rate in the TF coil copper stabilizer, nuclear heating in the epoxybased insulation material and TF coil, and energy multiplication were estimated. The cross section sensitivity study was performed using the sensitivity analysis code SWANLAKE. It shows that the copper atomic displacement rate in the inboard TF coil is known within + or - 24%. The nuclear heating in the inboard insulation material and TF coil are known within + or - 21% and + or - 12.5%, respectively. The uncertainties are primarily due to the iron inelastic scattering cross sections in the 14 MeV energy range.

  12. Consistent generation and functionalization of one-dimensional cross sections for TRAC-BF1

    SciTech Connect (OSTI)

    Munoz-Cobo, J.L.; Verdu, G.; Pereira, C.; Escriva, A.; Rodenas, J. . Dept. of Chemical and Nuclear Engineering); Castrillo, F.; Serra, J. )

    1994-08-01

    A method of calculation of correct functionalized cross sections and diffusion coefficients for TRAC-BF1, based on the one-dimensional kinetic files of the tridimensional simulator SIMULATE-3, is developed. The method allows the user to obtain first the consistent one-dimensional cross sections, diffusion coefficients, and bucklings, which upon being inserted into TRAC-BF1 conserve the three-dimensional eigenvalues, the planar reaction rates, and the fast and thermal radially averaged fluxes at each axial node. This method also compensates for the differences between the thermal-hydraulic models of the three-dimensional simulator and the transient analysis code. The errors obtained with this method are very small.

  13. POINT 2015: ENDF/B-VII.1 Final Temperature Dependent Cross Section Library

    Energy Science and Technology Software Center (OSTI)

    2015-06-01

    Version 00 For use in applications the ENDF/B-VII.1 library has been processed into the form of temperature dependent cross sections at eight neutron reactor like temperatures, between 0 K and 2100 K, in steps of 300 K (the exception being 293.6 K, for exact room temperature at 20 Celsius). It has also been processed to five astrophysics like temperatures—1, 10, and 100 eV; and 1 and 10 keV. For reference purposes, 300 K is approximatelymore » 1/40 eV, so that 1 eV is approximately 12,000 K. At each temperature the cross sections are tabulated and linearly interpolable in energy.« less

  14. Determination of partial (n,xngamma) cross-sections in 193-Ir

    SciTech Connect (OSTI)

    Talou, P; Chadwick, M B; Nelson, R; Fotiades, N; Devlin, M; Garrett, P E; Younes, W; Becker, J A

    2003-10-15

    The {sup 193}Ir(n,n'){sup 193m}Ir cross section for the production of the 80-keV isomer in {sup 193}Ir is evaluated using a combination of experimental data and nuclear reaction modeling, from threshold to about 20 MeV. Four discrete {gamma} lines feeding the isomer were recently observed with the GEANIE {gamma}-ray detector at LANSCE. Theoretical calculations of the nuclear reaction mechanisms in play are then carried out to evaluate the contributions not accounted for in the experimental setup (direct population; fraction of {gamma}-lines not observed in the experiment; etc). Experiment and modeling are then combined to provide a total cross section for the production of the Iridium isomer. We finally compare our result with activation measurement data available for a few energy points.

  15. CC-inclusive cross section measured with the T2K near detector

    SciTech Connect (OSTI)

    Weber, Alfons

    2015-05-15

    T2K has performed the first measurement of muon neutrino inclusive charged current interactions on carbon at neutrino energies of ?1 GeV where the measurement is reported as a flux-averaged double differential cross section in muon momentum and angle. The flux is predicted by the beam Monte Carlo and external data, including the results from the NA61/SHINE experiment. The data used for this measurement were taken in 2010 and 2011, with a total of 1.08*10{sup 20} protons-on-target. The analysis is performed on 4485 inclusive charged current interaction candidates selected in the most upstream fine-grained scintillator detector of the near detector. The flux-averaged total cross section is = (6.910.13(stat)0.84(syst)) 10{sup ?39} cm{sup 2}/nucleon for a mean neutrino energy of 0.85 GeV.

  16. Beauty production cross section measurements at E(cm) = 1.96-TeV

    SciTech Connect (OSTI)

    D'Onofrio, Monica; /Geneva U.

    2005-05-01

    The RunII physics program at the Tevatron started in spring 2001 with protons and antiprotons colliding at an energy of {radical}s = 1.96 TeV, and it is carrying on with more than 500 pb{sup -1} of data as collected by both the CDF and D0 experiments. Recent results on beauty production cross section measurements are here reported.

  17. W/Z production cross sections and asymmetries at E(CM) = 2-TeV

    SciTech Connect (OSTI)

    Bellavance, Angela M.; /Nebraska U.

    2005-06-01

    The most recent results for W and Z boson production cross sections and asymmetries are presented from the CDF and D0 collaborations using Run II data taken at the Fermi National Accelerator Laboratory (FNAL) Tevatron. Data set sizes range from 72 pb{sup -1} to 226 pb{sup -1}, and results range from published to preliminary. Results presented agree with the Standard Model and world averages within errors.

  18. Covariant Methods for Calculating Differential Cross Sections and Polarization Characteristics of Reactions

    SciTech Connect (OSTI)

    Sikach, S.M.

    2005-06-01

    A covariant method for calculating reaction amplitudes in the diagonal spin basis is presented. In this basis, amplitudes represent the spin kinematics of the interacting particles in the simplest and most adequate manner. A matrix is obtained such that differential cross sections for polarized particles and amplitude combinations that are required to calculate various polarization characteristics of reactions can be expressed in an arbitrary basis in terms of the amplitudes calculated in one basis.

  19. New approach to analyzing and evaluating cross sections for partial photoneutron reactions

    SciTech Connect (OSTI)

    Varlamov, V. V. Ishkhanov, B. S.; Orlin, V. N.

    2012-11-15

    The presence of substantial systematic discrepancies between the results of different experiments devoted to determining cross sections for partial photoneutron reactions-first of all, ({gamma}, n), ({gamma}, 2n), and ({gamma}, 3n) reactions-is a strong motivation for studying the reliability and authenticity of these data and for developing methods for taking into account and removing the discrepancies in question. In order to solve the first problem, we introduce objective absolute criteria involving transitional photoneutron-multiplicity functions F{sub 1}, F{sub 2}, F{sub 3}, Horizontal-Ellipsis ; by definition, their values cannot exceed 1.0, 0.5, 0.33, Horizontal-Ellipsis , respectively. With the aim of solving the second problem, we propose a new experimental-theoretical approach. In this approach, reaction cross sections are evaluated by simultaneously employing experimental data on the cross section for the total photoneutron yield, {sigma}{sup expt}({gamma}, xn) = {sigma}{sup expt}({gamma}, n) + 2{sigma}{sup expt}({gamma}, 2n) + 3{sigma}{sup expt}({gamma}, 3n) + Horizontal-Ellipsis , which are free from drawbacks plaguing experimental methods for sorting neutrons in multiplicity, and the results obtained by calculating the functions F{sub theor}{sup 1}, F{sub theor}{sup 2}, F{sub theor}{sup 3}, Horizontal-Ellipsis on the basis of the modern model of photonuclear reactions. The reliability and authenticity of data on the cross sections for ({gamma}, n), ({gamma}, 2n), and ({gamma}, 3n) partial reactions-{sigma}{sup eval}({gamma}, in) = F{sub i}{sup theor}{sigma}{sup expt}({gamma}, xn)-were evaluated for the {sup 90}Zr, {sup 115}In, {sup 112,114,116,117,118,119,120,122,124}Sn, {sup 159}Tb, and {sup 197}Au nuclei.

  20. Particle-driven gravity currents in non-rectangular cross section channels

    SciTech Connect (OSTI)

    Zemach, T.

    2015-10-15

    We consider a high-Reynolds-number gravity current generated by suspension of heavier particles in fluid of density ρ{sub i}, propagating along a channel into an ambient fluid of the density ρ{sub a}. The bottom and top of the channel are at z = 0, H, and the cross section is given by the quite general −f{sub 1}(z) ≤ y ≤ f{sub 2}(z) for 0 ≤ z ≤ H. The flow is modeled by the one-layer shallow-water equations obtained for the time-dependent motion which is produced by release from rest of a fixed volume of mixture from a lock. We solve the problem by the finite-difference numerical code to present typical height h(x, t), velocity u(x, t), and volume fraction of particles (concentration) ϕ(x, t) profiles. The methodology is illustrated for flow in typical geometries: power-law (f(z) = z{sup α} and f(z) = (H − z){sup α}, where α is positive constant), trapezoidal, and circle. In general, the speed of propagation of the flows driven by suspensions decreases compared with those driven by a reduced gravity in homogeneous currents. However, the details depend on the geometry of the cross section. The runout length of suspensions in channels of power-law cross sections is analytically predicted using a simplified depth-averaged “box” model. The present approach is a significant generalization of the classical gravity current problem. The classical formulation for a rectangular channel is now just a particular case, f(z) = const., in the wide domain of cross sections covered by this new model.

  1. JEF 2.2 Cross Section Library for the MCNP Monte Carlo Code.

    Energy Science and Technology Software Center (OSTI)

    2003-11-24

    Version 01 This continuous energy cross-section data library for MCNP is based on the JEF-2.2 evaluated nuclear data library (ACE format). The present library was satisfactorily tested in thermal and fast criticality benchmarks. For analyses below 20 MeV, MCJEF22NEA.BOLlB was applied also in cell and core calculations dedicated to the study of the subcritical accelerator driven systems (ADS).

  2. Nuclear Reaction Cross Sections Database at BNL | U.S. DOE Office of

    Office of Science (SC) Website

    Science (SC) Reaction Cross Sections Database at BNL Nuclear Physics (NP) NP Home About Research Facilities Science Highlights Benefits of NP Applications of Nuclear Science Applications of Nuclear Science Archives Small Business Innovation Research / Small Business Technology Transfer Funding Opportunities Nuclear Science Advisory Committee (NSAC) Community Resources Contact Information Nuclear Physics U.S. Department of Energy SC-26/Germantown Building 1000 Independence Ave., SW

  3. Estimating Three-Dimensional Cloudy Radiative Transfer Effects from Time-Height Cross Sections

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

    Estimating Three-Dimensional Cloudy Radiative Transfer Effects from Time-Height Cross Sections C. Hannay and R. Pincus National Oceanic and Atmospheric Administration Climate Diagnostics Center Boulder, Colorado K. F. Evans Program in Atmospheric and Oceanic Sciences University of Colorado Boulder, Colorado Introduction Clouds in the atmosphere are finite in extent and variable in every direction and in time. Long data sets from ground-based profilers, such as lidars or cloud radars, could

  4. MCNP Continuous-Energy Neutron Cross Section Libraries for Temperatures from 300 to 1365K.

    Energy Science and Technology Software Center (OSTI)

    2001-04-19

    Version 00 UTXS is a project whereby continuous-energy cross section libraries in ACE format suitable for the MCNP code were generated using the NJOY94.105 processing code. Libraries for various materials were generated at typical operating temperatures of the US Pressurized Water Reactor (PWR), Boiling Water Reactor (BWR), and the Russian PWR (VVER) as well as libraries for other non-reactor applications such as nuclear medicine.

  5. SENSIT-2D: a two-dimensional cross-section sensitivity and uncertainty analysis code

    SciTech Connect (OSTI)

    Embrechts, M.J.

    1982-10-01

    SENSIT-2D is a computer program that calculates the sensitivity and/or uncertainty for an integral response (e.g., heating, radiation damage), obtained from the two-dimensional discrete ordinates transport code TRIDENT-CTR, to the cross sections and cross-section uncertainties. A design-sensitivity option allows one to calculate the integral response when the cross sections in certain regions are changed. A secondary-energy-distribution sensitivity- and uncertainty-analysis capability is included. SENSIT-2D incorporates all the essential features of TRIDENT-CTR (r,z geometry option, triangular mesh, nonorthogonal boundaries, group-dependent quadrature sets) and is aimed at the needs of the fusion community. The structure of SENSIT-2D is similar to the structure of the SENSIT code, a one-dimensional sensitivity- and uncertainty-analysis code. This report covers the theory used in SENSIT-2D, outlines the code structure, and gives detailed input specifications. Where appropriate, parts of the SENSIT report are taken over in this write-up. Two sample problems which illustrate the use of SENSIT-2D are explained.

  6. Cross section measurements for quasi-elastic neutrino-nucleus scattering with the MINOS near detector

    SciTech Connect (OSTI)

    Dorman, Mark Edward; /University Coll. London

    2008-04-01

    The Main Injector Neutrino Oscillation Search (MINOS) is a long baseline neutrino oscillation experiment based at the Fermi National Accelerator Laboratory (FNAL) in Chicago, Illinois. MINOS measures neutrino interactions in two large iron-scintillator tracking/sampling calorimeters; the Near Detector on-site at FNAL and the Far Detector located in the Soudan mine in northern Minnesota. The Near Detector has recorded a large number of neutrino interactions and this high statistics dataset can be used to make precision measurements of neutrino interaction cross sections. The cross section for charged-current quasi-elastic scattering has been measured by a number of previous experiments and these measurements disagree by up to 30%. A method to select a quasi-elastic enriched sample of neutrino interactions in the MINOS Near Detector is presented and a procedure to fit the kinematic distributions of this sample and extract the quasi-elastic cross section is introduced. The accuracy and robustness of the fitting procedure is studied using mock data and finally results from fits to the MINOS Near Detector data are presented.

  7. Nucleus-nucleus total reaction cross sections, and the nuclear interaction radius

    SciTech Connect (OSTI)

    Abu-Ibrahim, Badawy

    2011-04-15

    We study the nucleus-nucleus total reaction cross sections for stable nuclei, in the energy region from 30A MeV to about 1A GeV, and find them to be in proportion to ({radical}({sigma}{sub pp}{sup tot}Z{sub 1}{sup 2/3}+{sigma}{sub pn}{sup tot}N{sub 1}{sup 2/3})+{radical}({sigma}{sub pp}{sup tot}Z{sub 2}{sup 2/3}+{sigma}{sub pn}{sup tot}N{sub 2}{sup 2/3})) {sup 2} in the mass range 8 to 100. Also, we find a parameter-free relation that enables us to predict a total reaction cross section for any nucleus-nucleus within 10% uncertainty at most, using the experimental value of the total reaction cross section of a given nucleus-nucleus. The power of the relation is demonstrated by several examples. The energy dependence of the nuclear interaction radius is deduced; it is found to be almost constant in the energy range from about 200A MeV to about 1A GeV; in this energy range and for nuclei with N=Z, R{sub I}(A)=(1.14{+-}0.02)A{sup 1/3} fm.

  8. Measurements of the W production cross sections in association with jets with the ATLAS detector

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

    Aad, G.

    2015-02-19

    This paper presents cross sections for the production of a W boson in association with jets, measured in proton–proton collisions at \\(\\sqrt{s} = 7\\) TeV with the ATLAS experiment at the large hadron collider. With an integrated luminosity of 4.6fb-1, this data set allows for an exploration of a large kinematic range, including jet production up to a transverse momentum of 1TeV and multiplicities up to seven associated jets. The production cross sections for W bosons are measured in both the electron and muon decay channels. Differential cross sections for many observables are also presented including measurements of the jetmore » observables such as the rapidities and the transverse momenta as well as measurements of event observables such as the scalar sums of the transverse momenta of the jets. As a result, the measurements are compared to numerous QCD predictions including next-to-leading-order perturbative calculations, resummation calculations and Monte Carlo generators.« less

  9. Elastic and inelastic neutron scattering cross sections for fission reactor applications

    SciTech Connect (OSTI)

    Hicks, S. F.; Combs, B.; Downes, L.; Girgis, J.; Kersting, L. J.; Lueck, C. J.; McDonough, P. J.; Schniederjan, J.; Sidwell, L.; Sigillito, A. J.; Chakraborty, A.; Crider, B. P.; Kumar, A.; McEllistrem, M. T.; Peters, E. E.; Prados-Estevz, F. M.; Vanhoy, J. R.; Watts, D.; Yates, S. W.

    2013-04-19

    Nuclear data important for the design and development of the next generation of light-water reactors and future fast reactors include neutron elastic and inelastic scattering cross sections on important structural materials, such as Fe, and on coolant materials, such as Na. These reaction probabilities are needed since neutron reactions impact fuel performance during irradiations and the overall efficiency of reactors. While neutron scattering cross sections from these materials are available for certain incident neutron energies, the fast neutron region, particularly above 2 MeV, has large gaps for which no measurements exist, or the existing uncertainties are large. Measurements have been made at the University of Kentucky Accelerator Laboratory to measure neutron scattering cross sections on both Fe and Na in the region where these gaps occur and to reduce the uncertainties on scattering from the ground state and first excited state of these nuclei. Results from measurements on Fe at incident neutron energies between 2 and 4 MeV will be presented and comparisons will be made to model calculations available from data evaluators.

  10. Copper K-shell emission cross sections for lasersolid experiments

    SciTech Connect (OSTI)

    Davies, J. R.; Betti, R.; Nilson, P. M.; Solodov, A. A.

    2013-08-15

    Published measurements and models of the cross section for electrons causing K-shell emission from copper are reviewed to find a suitable expression to use when analyzing K{sub ?}-emission measurements in lasersolid experiments at peak intensities above 10{sup 18} W/cm{sup 2}. Few measurements exist in the 0.1- to 10-MeV electron energy range currently of interest, leaving a number of possible suitable models that are summarized here with a number of typing errors corrected. Two different limiting forms for the cross section at relativistic energies are used, and existing measurements do not give a clear indication as to which is correct. Comparison with the limiting form of electron stopping power indicates an alternative relativistic form and also that the density-effect correction will be important in copper above 10 MeV. For data analysis relying on relative K{sub ?} emission caused by electrons with energy much greater than the K-shell binding energy, the existing uncertainty in cross sections is unimportant, but it will be a source of uncertainty when using absolute values and for electron energies up to ?6 the binding energy. K-shell emission caused by photons and protons is also briefly reviewed.