Ratio of Capture to Fission in Pu-239 at Kev Neutron Energies

Ratio of Capture to Fission in Pu-239 at Kev Neutron Energies PDF Author:
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ISBN:
Category :
Languages : en
Pages : 19

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Ratio of Capture to Fission in Pu-239 at Kev Neutron Energies

Ratio of Capture to Fission in Pu-239 at Kev Neutron Energies PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 19

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Radiative Capture-to-fission Cross-section Ratio for Plutonium-239 in the Neutron Energy Region Below ~ 50 KeV

Radiative Capture-to-fission Cross-section Ratio for Plutonium-239 in the Neutron Energy Region Below ~ 50 KeV PDF Author: A.A. Bergman
Publisher:
ISBN:
Category : Capture
Languages : en
Pages : 10

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Measurement of the Ratio of the Radiative Capture to Fission Cross Sections (alpha) for Pu-239 in the Neutron Energy Range 0.1 to 30 KeV

Measurement of the Ratio of the Radiative Capture to Fission Cross Sections (alpha) for Pu-239 in the Neutron Energy Range 0.1 to 30 KeV PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 16

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The Ratio of Thermal Neutron Capture to Fission for 239U

The Ratio of Thermal Neutron Capture to Fission for 239U PDF Author: G. D. James
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Category : Alpha rays
Languages : en
Pages : 24

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Mass Ratios and Energy Released in the Fission of U235 and Pu239 by Thermal Neutrons

Mass Ratios and Energy Released in the Fission of U235 and Pu239 by Thermal Neutrons PDF Author: Martin Deutsch
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Category : Nuclear fission
Languages : en
Pages : 20

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Nuclear Data and Measurements Series

Nuclear Data and Measurements Series PDF Author:
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Category :
Languages : en
Pages :

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The prompt-fission-neutron spectrum resulting from 239Pu fission induced by 0.55 MeV incident neutrons is measured from 1.0 to 10.0 MeV relative to that of 235U fission induced by the same incident-energy neutrons. The measurements employ the time-of-flight technique. Energy-dependent ratios of the two spectra are deduced from the measured values over the energy range 1.0 to 10.0 MeV. The experimentally-derived ratio results are compared with those calculated from ENDF/B-V, revision-2, and with results of recent microscopic measurements. Using the ENDF/B-V 235U Watt parameters for the 235U spectrum, the experimental measurements imply a ratio of average fission-spectrum energies of 239Pu/235U = 1.045 +- 0.003, compared to the value 1.046 calculated from ENDF/B-V, revision 2. 12 refs., 2 figs., 2 tabs.

The Ratio on Neutron Capture to Fission for Uranium 235

The Ratio on Neutron Capture to Fission for Uranium 235 PDF Author: M.J. Cabell
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ISBN:
Category :
Languages : en
Pages : 14

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The Ratio of Neutron Capture to Fission for Uranium 233

The Ratio of Neutron Capture to Fission for Uranium 233 PDF Author: M.J. Cabell
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Category :
Languages : en
Pages : 15

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The Ratio of Neutron Capture to Fission in U235

The Ratio of Neutron Capture to Fission in U235 PDF Author: R. W. Jones
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Category : Fission
Languages : en
Pages : 19

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Kev Neutron Capture and Fission Measurements on PU 242

Kev Neutron Capture and Fission Measurements on PU 242 PDF Author: Andrew J. Sanislo
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ISBN:
Category :
Languages : en
Pages : 125

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