Neutron inelastic scattering from some odd-mass nuclei in the energy range 2.0 to 4.5 MeV

Ramström, E.

doi:10.1016/0375-9474(79)90639-0

Cited by 10 publications

(1 citation statement)

References 26 publications

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“…Furthermore, the experimental elastic scattering data were corrected for neutron flux attenuation and multiple scattering in the sample as well as for the finite scattering geometry using an improved version of the Monte Carlo code MULTSCAT4 (Holmqvist et al 1967). The inelastic scattering data were corrected for flux attenuation and for in-and out-scattering of neutrons to or from the state under consideration (Almen-Ramstrom 1975). Corrections for attenuation and multiple scattering in the polyethylene sample were carried out by applying the analytically expressed correction factor given by Olsson and Trostell (1986).…”

Section: Data Reduction and Experimental Resultsmentioning

confidence: 99%

Cross sections and partial kerma factors for elastic and inelastic neutron scattering from carbon in the energy range 16.5-22.0 MeV

Olsson¹,

Trostell²,

Ramström³

1989

Phys. Med. Biol.

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The Studsvik high resolution, low background time-of-flight facility has been used to obtain a comprehensive set of differential neutron scattering cross sections for carbon at the neutron energies 16.5, 17.6, 18.7, 19.8, 20.9, 21.6 and 22.0 MeV. Angular distributions in the range 10-160" have been measured for elastic scattering, and also for inelastic scattering from the levels at 4.44, 7.65 and 9.64 MeV. Angle integrated cross sections have been determined by fitting Legendre polynomial expansions to the differential data. Partial kerma factors for elastic and inelastic (4.44MeV level) scattering have been deduced from these fits. Analyses in terms of a spherical optical model as well as in terms of the coupled-channels formalism with a deformed potential have provided information for cross section and partial kerma factor calculations also outside the measured energy range.

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Section: Data Reduction and Experimental Resultsmentioning

confidence: 99%

Cross sections and partial kerma factors for elastic and inelastic neutron scattering from carbon in the energy range 16.5-22.0 MeV

Olsson¹,

Trostell²,

Ramström³

1989

Phys. Med. Biol.

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Inelastic Scattering Cross Sections in the Energy Range 2.0 to 4.5 MeV Calculated With Different Formalisms for Level Width Fluctuation Corrections

Ramström

1983

Nuclear Data for Science and Technology

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Statistical model calculations for medium and strong absorption in theA=90 region

Vlăducă

Stan-Sion

Berinde³

et al. 1980

Z Physik A

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Calculations of elastic, inelastic and total neutron cross sections as well as of (p,n) reaction cross sections in the A--90 mass region have been performed, using the statistical model of Hofmann, Richert, Tepel and Weidenmiiller. The optical model parameters were obtained by Finckh etal. from the neutron decay of IAR in the 91Zr(p, n)9aNb reaction. The calculations are in very good agreement with the published experimental data. The optical model parameters proved to be satisfactory up to about E, = 8.0 MeV. The present work might be relevant to the evaluation of neutron data for reactor technology.

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Neutron inelastic scattering from some odd-mass nuclei in the energy range 2.0 to 4.5 MeV

Cited by 10 publications

References 26 publications

Cross sections and partial kerma factors for elastic and inelastic neutron scattering from carbon in the energy range 16.5-22.0 MeV

Cross sections and partial kerma factors for elastic and inelastic neutron scattering from carbon in the energy range 16.5-22.0 MeV

Inelastic Scattering Cross Sections in the Energy Range 2.0 to 4.5 MeV Calculated With Different Formalisms for Level Width Fluctuation Corrections

Statistical model calculations for medium and strong absorption in theA=90 region

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