Calculation of Prompt Fission Neutron Spectra. [0. 53 MeV].

Calculation of Prompt Fission Neutron Spectra. [0. 53 MeV]. PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Book Description
A new calculation of the prompt fission neutron spectrum N(E) is presented as a function of both the fissioning nucleus and its excitation energy. The calculation, based upon standard nuclear-evaporation theory, accounts for the physical effects of the distribution of fission-fragment residual nuclear temperature and the energy dependence of the cross section for the inverse process of compound-nucleus formation. With the use of a residual nuclear temperature distribution based upon the Fermi-gas model, calculations were performed for two different assumptions concerning the cross section for compound-nucleus formation. Use of a constant cross section leads to a closed expression for the neutron energy spectrum, while use of an energy-dependent cross section, calculated with the optical model, yields a numerical integration. Results obtained for the two assumptions agree well with experimental data, although there is a preference for the energy-dependent cross section calculation. 7 figures.

Calculation of Prompt Fission Neutron Spectra. [0. 53 MeV].

Calculation of Prompt Fission Neutron Spectra. [0. 53 MeV]. PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Book Description
A new calculation of the prompt fission neutron spectrum N(E) is presented as a function of both the fissioning nucleus and its excitation energy. The calculation, based upon standard nuclear-evaporation theory, accounts for the physical effects of the distribution of fission-fragment residual nuclear temperature and the energy dependence of the cross section for the inverse process of compound-nucleus formation. With the use of a residual nuclear temperature distribution based upon the Fermi-gas model, calculations were performed for two different assumptions concerning the cross section for compound-nucleus formation. Use of a constant cross section leads to a closed expression for the neutron energy spectrum, while use of an energy-dependent cross section, calculated with the optical model, yields a numerical integration. Results obtained for the two assumptions agree well with experimental data, although there is a preference for the energy-dependent cross section calculation. 7 figures.

Recent Improvements in the Calculation of Prompt Fission Neutron Spectra

Recent Improvements in the Calculation of Prompt Fission Neutron Spectra PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Book Description
Three tropics have been considered in the refinement and improvement of our original calculations of prompt fission neutron spectra. These are an improved calculation of the prompt fission neutron spectrum N(E) from the spontaneous fission of 252Cf, a complete calculation of the prompt fission neutron spectrum matrix N(E, E/sub n/) from the neutron-induced fission of 235U, at incident neutron energies ranging from 0 to 15 MeV, and an assessment of the scission neutron component of the prompt fission neutron spectrum. Preliminary results will be presented and compared with experimental measurements and an evaluation. A suggestion has been made for new integral cross-section measurements.

Fission Neutrons

Fission Neutrons PDF Author: Nikolay Kornilov
Publisher: Springer
ISBN: 3319071335
Category : Science
Languages : en
Pages : 135

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Book Description
Although the fission of heavy nuclei was discovered over 75 years ago, many problems and questions still remain to be addressed and answered. The reader will be presented with an old, but persistent problem of this field: The contradiction between Prompt Fission Neutron (PFN) spectra measured with differential (microscopic) experiments and integral (macroscopic and benchmark) experiments (the Micro-Macro problem). The difference in average energy is rather small ~3% but it is stable and we cannot explain the difference due to experimental uncertainties. Can we measure the PFN spectrum with high accuracy? How may we compare results of different experiments to provide better accuracy? Are our traditional theoretical models correct? What can be done to solve the Micro-Macro problem in future? These questions are discussed in this monograph for the reader. The current work will be of interest to graduate students and researchers, particularly those working in nuclear and neutron physics.

Nuclear Cross Sections for Technology

Nuclear Cross Sections for Technology PDF Author: Joseph L. Fowler
Publisher:
ISBN:
Category : Cross sections (Nuclear physics)
Languages : en
Pages : 1064

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Book Description


Calculation of Fission Spectrum Integrals for the Energyregion15-20 MeV of Fission Neutron Spectra

Calculation of Fission Spectrum Integrals for the Energyregion15-20 MeV of Fission Neutron Spectra PDF Author: R. L. Walsh
Publisher:
ISBN:
Category :
Languages : en
Pages : 8

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NBS Special Publication

NBS Special Publication PDF Author:
Publisher:
ISBN:
Category : Weights and measures
Languages : en
Pages : 1058

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New Calculation of Prompt Fission Neutron Spectra and Average Prompt Neutron Multiplicities

New Calculation of Prompt Fission Neutron Spectra and Average Prompt Neutron Multiplicities PDF Author: David G. Madland
Publisher:
ISBN:
Category : Fission fragments
Languages : en
Pages : 166

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Book Description


Prompt Fission Neutron Spectra

Prompt Fission Neutron Spectra PDF Author: International Atomic Energy Agency
Publisher:
ISBN:
Category : Fast neutrons
Languages : en
Pages : 206

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Book Description


Improved Calculation of the Prompt Fission Neutron Spectrum from the Spontaneous Fission of 252Cf

Improved Calculation of the Prompt Fission Neutron Spectrum from the Spontaneous Fission of 252Cf PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Book Description
An improved calculation is presented for the prompt fission neutron spectrum N(E) from the spontaneous fission of 252Cf. In this calculation the fission-spectrum model of Madland and Nix is used, but with several improvements leading to a physically more accurate representation of the spectrum. Specifically, the contributions to N(E) from the entire fission-fragment mass and charge distributions will be calculated instead of calculating on the basis of a seven-point approximation to the peaks of these distributions as has been done in the past. Therefore, values of the energy release in fission, fission-fragment kinetic energy, nuclear level density, and compound nucleus cross section for the inverse process will be considered on a point-by-point basis over the fragment yield distributions instead of considering averages of these quantities over the peaks of the distributions. Particular attention will be given to the energy-dependent compound nucleus cross sections and to the nuclear level density model. Other refinements to the calculation of N(E) will also be discussed. Results will be presented and compared with earlier calculations of the spectrum and with recent experimental measurements of the spectrum. 9 figs.

Improved Calculation of the Prompt Fission Neutron Spectrum from the Spontaneous Fission of 252Cf

Improved Calculation of the Prompt Fission Neutron Spectrum from the Spontaneous Fission of 252Cf PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Book Description
An improved calculation is presented for the prompt fission neutron spectrum N(E) from the spontaneous fission of 252Cf. In this calculation the fission-spectrum model of Madland and Nix is used, but with several improvements leading to a physically more accurate representation of the spectrum. Specifically, the contributions to N(E) from the entire fission-fragment mass and charge distributions will be calculated instead of calculating on the basis of a seven- point approximation to the peaks of these distributions as has been done in the past. Therefore, values of the energy release in fission, fission-fragment kinetic energy, and compound nucleus cross section for the inverse process will be considered on a point-by-point basis over the fragment yield distributions instead of considering averages of these quantities over the peaks of the distributions. Preliminary results will be presented and compared with a measurement, an earlier calculation, and a recent evaluation of the spectrum. 14 refs., 4 figs.