Author: Suresh C. Mathur
Publisher:
ISBN:
Category :
Languages : en
Pages : 177
Book Description
To check the inelastic neutron scattering cross sections previously measured, the entire experiment was repeated by use of neutron time-of-flight techniques. In particular, the neutron inelastic scattering cross sections were measured for the following elements with an incident neutron energy of 15 MeV: (1) at 90 deg. for Be, B10, B, C, Mg, Si, Mn, Fe, Co, Ni, Cu, Se, Mo, Cd, W, Pb, Ce, Sb, V, Y and Ti; (2) at scattering angles of 30, 40, 55, 70, 90, and 125 deg. for Be, Co, Mo, Cd and W.A computer code MULTSCAT was developed to obtain the corrections due to multiple scattering of neutrons in the scatterer. This code was compiled in Fortran-63 language for a CDC-1604 computer. The experimental cross sections obtained in the present project were corrected for double scattering by means of the MULTSCAT code. (Author).
Inelastic Neutron Scattering Cross Sections in Several Elements with 15 Mev Neutrons
Author: Suresh C. Mathur
Publisher:
ISBN:
Category :
Languages : en
Pages : 177
Book Description
To check the inelastic neutron scattering cross sections previously measured, the entire experiment was repeated by use of neutron time-of-flight techniques. In particular, the neutron inelastic scattering cross sections were measured for the following elements with an incident neutron energy of 15 MeV: (1) at 90 deg. for Be, B10, B, C, Mg, Si, Mn, Fe, Co, Ni, Cu, Se, Mo, Cd, W, Pb, Ce, Sb, V, Y and Ti; (2) at scattering angles of 30, 40, 55, 70, 90, and 125 deg. for Be, Co, Mo, Cd and W.A computer code MULTSCAT was developed to obtain the corrections due to multiple scattering of neutrons in the scatterer. This code was compiled in Fortran-63 language for a CDC-1604 computer. The experimental cross sections obtained in the present project were corrected for double scattering by means of the MULTSCAT code. (Author).
Publisher:
ISBN:
Category :
Languages : en
Pages : 177
Book Description
To check the inelastic neutron scattering cross sections previously measured, the entire experiment was repeated by use of neutron time-of-flight techniques. In particular, the neutron inelastic scattering cross sections were measured for the following elements with an incident neutron energy of 15 MeV: (1) at 90 deg. for Be, B10, B, C, Mg, Si, Mn, Fe, Co, Ni, Cu, Se, Mo, Cd, W, Pb, Ce, Sb, V, Y and Ti; (2) at scattering angles of 30, 40, 55, 70, 90, and 125 deg. for Be, Co, Mo, Cd and W.A computer code MULTSCAT was developed to obtain the corrections due to multiple scattering of neutrons in the scatterer. This code was compiled in Fortran-63 language for a CDC-1604 computer. The experimental cross sections obtained in the present project were corrected for double scattering by means of the MULTSCAT code. (Author).
Elastic and Inelastic Neutron Cross Sections
Author: Devereux L. Kavanagh
Publisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 162
Book Description
Publisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 162
Book Description
The Status of Experimental Neutron Cross Sections for Energies Between 0.5 and 14.5 Mev
Author: Robert J. Howerton
Publisher:
ISBN:
Category : Elastic scattering
Languages : en
Pages : 28
Book Description
Publisher:
ISBN:
Category : Elastic scattering
Languages : en
Pages : 28
Book Description
Scientific and Technical Aerospace Reports
Author:
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 1330
Book Description
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 1330
Book Description
Conference on Neutron Cross Section Technology
Author: P. B. Hemmig
Publisher:
ISBN:
Category : Neutron cross sections
Languages : en
Pages : 572
Book Description
Publisher:
ISBN:
Category : Neutron cross sections
Languages : en
Pages : 572
Book Description
Measurement of Transport and Inelastic Scattering Cross Section for Fast Neutrons
Author:
Publisher:
ISBN:
Category : Fast neutrons
Languages : en
Pages : 34
Book Description
Publisher:
ISBN:
Category : Fast neutrons
Languages : en
Pages : 34
Book Description
U.S. Government Research Reports
Author:
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 198
Book Description
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 198
Book Description
Technical Abstract Bulletin
Author:
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 912
Book Description
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 912
Book Description
Neutrons Scattering and Gamma-Ray Production Cross Sections for N, O, Al, Si, Ca and Fe
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 113
Book Description
Measurements of neutron elastic and inelastic scattering and gamma- ray production have been made on several elements with 9.0 and 11.0 MeV incident neutrons. Differential cross sections for N, O, Al, Si, Ca, and Fe are presented and integral cross sections derived from the data are also given.
Publisher:
ISBN:
Category :
Languages : en
Pages : 113
Book Description
Measurements of neutron elastic and inelastic scattering and gamma- ray production have been made on several elements with 9.0 and 11.0 MeV incident neutrons. Differential cross sections for N, O, Al, Si, Ca, and Fe are presented and integral cross sections derived from the data are also given.
Nuclear Cross Sections for 95-Mev Neutrons
Author: James DeJuren
Publisher:
ISBN:
Category : Bismuth
Languages : en
Pages : 24
Book Description
The total cross sections of twelve different elements were measured using the neutron beam from the 184-in. cyclotron, operating with deuterons. Bismuth fission ionization chambers were employed as both monitor and detector in conventional 'good geometry' attenuation measurements in the neutron flux emerging from the 3-in. diameter collimating port in the 10-ft-thick concrete shielding. The mean energy of detection of the neutrons in this experiment is estimated to be 95 Mev. Measurements were also made with a monitor and detector placed inside the concrete shielding where an intense neutron flux over a large area could be obtained. Attenuators of four different elements were placed in front of the detector in a 'poor geometry' arrangement so that attenuation was due essentially to inelastic collisions which degrade the neutron energy below the fission threshold. A second detector was placed outside the concrete shielding In the collimated neutron beam in line with the neutron source, absorber, and first detector. Attenuation in it is caused by both inelastic and elastic scattering. By this arrangement the ratio of inelastic to total cross section can be determined directly in one experiment. The nuclear radii as calculated from the observed cross section, using the theory of the transparent nucleus, vary as 1.38 x 10(exp-13) A(exp(1/3)) cm. In this energy range the ratios of the inelastic to total cross sections are all less than one-half.
Publisher:
ISBN:
Category : Bismuth
Languages : en
Pages : 24
Book Description
The total cross sections of twelve different elements were measured using the neutron beam from the 184-in. cyclotron, operating with deuterons. Bismuth fission ionization chambers were employed as both monitor and detector in conventional 'good geometry' attenuation measurements in the neutron flux emerging from the 3-in. diameter collimating port in the 10-ft-thick concrete shielding. The mean energy of detection of the neutrons in this experiment is estimated to be 95 Mev. Measurements were also made with a monitor and detector placed inside the concrete shielding where an intense neutron flux over a large area could be obtained. Attenuators of four different elements were placed in front of the detector in a 'poor geometry' arrangement so that attenuation was due essentially to inelastic collisions which degrade the neutron energy below the fission threshold. A second detector was placed outside the concrete shielding In the collimated neutron beam in line with the neutron source, absorber, and first detector. Attenuation in it is caused by both inelastic and elastic scattering. By this arrangement the ratio of inelastic to total cross section can be determined directly in one experiment. The nuclear radii as calculated from the observed cross section, using the theory of the transparent nucleus, vary as 1.38 x 10(exp-13) A(exp(1/3)) cm. In this energy range the ratios of the inelastic to total cross sections are all less than one-half.