Inelastic Cross Sections For Fission Spectrum Neutrons


Inelastic Cross Sections For Fission Spectrum Neutrons
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Inelastic Cross Sections For Fission Spectrum Neutrons


Inelastic Cross Sections For Fission Spectrum Neutrons
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Author : Hans Albrecht Bethe
language : en
Publisher:
Release Date : 1955

Inelastic Cross Sections For Fission Spectrum Neutrons written by Hans Albrecht Bethe and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1955 with Cross sections (Nuclear physics) categories.




Neutron Cross Sections And Technology


Neutron Cross Sections And Technology
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Author : David T. Goldman
language : en
Publisher:
Release Date : 1968

Neutron Cross Sections And Technology written by David T. Goldman and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1968 with Neutron cross sections categories.




Conference On Neutron Cross Section Technology


Conference On Neutron Cross Section Technology
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Author : P. B. Hemmig
language : en
Publisher:
Release Date : 1966

Conference On Neutron Cross Section Technology written by P. B. Hemmig and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1966 with Neutron cross sections categories.




Fast Reactor Cross Sections


Fast Reactor Cross Sections
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Author : Shimon Yiftah
language : en
Publisher:
Release Date : 1960

Fast Reactor Cross Sections written by Shimon Yiftah and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1960 with Fast nuclear reactors categories.




Fission Spectrum


Fission Spectrum
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Author : Felix Bloch
language : en
Publisher:
Release Date : 1951

Fission Spectrum written by Felix Bloch and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1951 with Neutrons categories.


Measurements of the spectrum of the fission neutrons of 25 are described, in which the energy of the neutrons is determined from the ionization produced by individual hydrogen recoils. The slow neutrons producing fission are obtained by slowing down the fast neutrons from the Be-D reaction of the Stanford cyclotron. In order to distinguish between fission neutrons and the remaining fast cyclotron neutrons both the cyclotron current and the pusle amplifier are modulated. A hollow neutron container, in which slow neutrons have a lifetime of about 2 milliseconds, avoids the use of large distances. This method results in much higher intensities than the usual modulation arrangement. The results show a continuous distribution of neutrons with a rather wide maximum at about 0.8 MV falling off to half of its maximum value at 2.0 MV. The total number of netrons is determined by comparison with the number of fission fragments. The result seems to indicate that only about 30% of the neutrons have energies below .8 MV. Various tests are described which were performed in order to rule out modification of the spectrum by inelastic scattering.



Six And Sixteen Group Cross Sections For Fast And Intermediate Critical Assemblies


Six And Sixteen Group Cross Sections For Fast And Intermediate Critical Assemblies
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Author : Gordon Edward Hansen
language : en
Publisher:
Release Date : 1961

Six And Sixteen Group Cross Sections For Fast And Intermediate Critical Assemblies written by Gordon Edward Hansen and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1961 with Neutron cross sections categories.




Neutron Scattering By U235 Pu239 And U238


Neutron Scattering By U235 Pu239 And U238
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Author : Lawrence Cranberg
language : en
Publisher:
Release Date : 1959

Neutron Scattering By U235 Pu239 And U238 written by Lawrence Cranberg and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1959 with Neutrons categories.




Reports To The Aec Nuclear Cross Sections Advisory Group


Reports To The Aec Nuclear Cross Sections Advisory Group
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Author :
language : en
Publisher:
Release Date : 1956-09

Reports To The Aec Nuclear Cross Sections Advisory Group written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1956-09 with Nuclear physics categories.




Proceedings


Proceedings
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Author : Conference on Neutron Cross Section Technology
language : en
Publisher:
Release Date : 1966

Proceedings written by Conference on Neutron Cross Section Technology and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1966 with Neutrons categories.




Nuclear Cross Sections For 95 Mev Neutrons


Nuclear Cross Sections For 95 Mev Neutrons
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Author : James DeJuren
language : en
Publisher:
Release Date : 1950

Nuclear Cross Sections For 95 Mev Neutrons written by James DeJuren and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1950 with Bismuth categories.


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.