Ni Elemental Neutron Induced Reaction Cross-section Evaluation

Ni Elemental Neutron Induced Reaction Cross-section Evaluation
Author:
Publisher:
Total Pages:
Release: 1979
Genre:
ISBN:

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A completely new evaluation of the nickel neutron induced reaction cross sections was undertaken as a part of the ENDF/B-V effort. (n, xy) reactions and capture reaction time from threshold to 20 MeV were considered for 58 6° 61 62 64Ni isotopes to construct the corresponding reaction cross section for natural nickel. Both experimental and theoretical calculated results were used in evaluating different partial cross sections. Precompound effects were included in calculating (n, xy) reaction cross sections. Experimentally measured total section data extending from 0.7 MeV to 20 MeV were used to generate smooth cross section. Below 0.7 to MeV elastic and capture cross sections are represented by resonance parameters. Inelastic angular distributions to the discrete isotopic levels and elemental elastic angular distributions are included in the evaluated data file. Gamma production cross sections and energy distribution due to capture and the (n, xy) reactions were evaluated from experimental data. Finally, error files are constructed for all partial cross sections.

Neutron Cross Sections

Neutron Cross Sections
Author: Victoria McLane
Publisher: Elsevier
Total Pages: 850
Release: 2012-12-02
Genre: Science
ISBN: 0323142222

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Neutron Cross Sections, Volume 2: Neutron Cross Section Curves presents data for total reaction cross sections and related fission parameters as a function of incident-neutron energy. This book covers energy range from 0.01 eV to 200 MeV to exclude crystalline and magnetic effects for slow neutrons and relativistic effects for high energy neutrons. The data in this volume are grouped into sections corresponding to the element of the target nucleus in the neutron-induced reaction. These sections are ordered in increasing atomic number. Within a section, graphical data are presented for the natural element followed by the isotopes of that element in order of increasing atomic mass. A list of the reaction types is provided at the end of each section. This book also provides graphical section, wherein each graphical page is annotated on the outer edge with a symbol for an element or isotope followed by the list of the cross section data for that element or isotope. The data plotted in the graphical section are tagged by a mnemonic consisting of year, laboratory, and author's last name. This tag can be used to find the corresponding reference on the bibliographic pages.

Neutron Cross-sections: Measurements & Evaluations

Neutron Cross-sections: Measurements & Evaluations
Author: Akm Moinul Haque Meaze
Publisher: LAP Lambert Academic Publishing
Total Pages: 152
Release: 2013
Genre:
ISBN: 9783659422164

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Neutrons are currently used across a vast extent of science. Neutron induced reaction cross-section is indispensable quantity of nuclear data, which is imperative in the applications of nuclear science and technologies. Precise resonance cross-sections are desired for the safety investigation, assessment of the neutron flux density, reaction rate, etc to drive the nuclear technologies such as nuclear power plant. Fission reaction cross-section is the key parameter for the feasibility studies and for designing next generation reactor. This book presents concrete concepts of neutron, neutron production, neutron induced reaction cross-sections, resonances and interrelated matters. Careful and detailed theoretical and contemporary experimental approaches of this text provide clear, correct, and up-to-date information in the field of neutron physics. With comprehensible discussion and numerous experimental results, this book adequately and widely covers all the major categories of neutron cross-sections.

ENDF-6 Compatible Evaluation of Neutron Induced Reaction Cross Sections for [sup]106,108,110,111,112,113,114,116Cd

ENDF-6 Compatible Evaluation of Neutron Induced Reaction Cross Sections for [sup]106,108,110,111,112,113,114,116Cd
Author: Ivan Sirakov
Publisher:
Total Pages: 8
Release: 2013
Genre:
ISBN: 9789279284212

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An ENDF-6 compatible evaluation for neutron induced reactions in the resonance region has been completed for 106,108,110,111,112,113,114,116Cd. The parameters are the result of an analysis of experimental data available in the literature together with a parameter adjustment on transmission and capture data obtained at the time-of-flight facility GELINA. Complete evaluated data files in ENDF-6 format have been produced by joining the evaluations in the resonance region with corresponding files from the JEFF-3.1.2 nuclear data library (or with the JEFF-Beta-CAD proposed evaluation in case of 113Cd). These files were produced for use in the JEFF32T2 library. For neutron induced reactions in the unresolved resonance region the JENDL 4.0 evaluation for 111Cd and 113Cd was adopted. The evaluated files have been processed with the latest updates of NJOY. 99 to test their format and application consistency as well as to produce a continuous-energy data library in ACE format for use in Monte Carlo codes. The ACE files have been utilized to study the effect of the evaluated resonance parameters on results of integral experiments. The evaluated files will be implemented in the next release of the JEFF-3 library which is maintained by the Nuclear Energy Agency of the OECD.

Measured and Evaluated Fast Neutron Cross Sections of Elemental Nickel

Measured and Evaluated Fast Neutron Cross Sections of Elemental Nickel
Author:
Publisher:
Total Pages:
Release: 1975
Genre:
ISBN:

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Fast neutron total and scattering cross sections of elemental nickel are measured. Differential elastic scattering cross sections are determined from incident energies of 0.3 to 4.0 MeV. The cross sections for the inelastic neutron excitation of states at: 1.156 +- 0.015, 1.324 +- 0.015, 1.443 +- 0.015, 2.136 +- 0.013, 2.255 +- 0.030, 2.449 +- 0.030, 2.614 +- 0.020 and 2.791 +- 0.025 MeV are measured to incident neutron energies of 4.0 MeV. The total neutron cross sections are determined from 0.25 to 5.0 MeV. The experimental results are discussed in the context of optical and statistical models. It is shown that resonance width-fluctuation and correlation effects are significant. The present experimental and theoretical results, together with previously reported values, are used to construct a comprehensive evaluated elemental data file in the ENDF format. Some comparisons are made with previously reported evaluated files. In addition, some selected reactions which are widely used in dosimetry and other applications are presented as supplemental evaluated isotopic-data files. The numerical quantities are presented in tabular form. (3 tables, 29 figures) (auth).

Evaluation of Neutron Induced Reaction Cross Sections on Gold

Evaluation of Neutron Induced Reaction Cross Sections on Gold
Author: Ivan Sirakov
Publisher:
Total Pages: 9
Release: 2013
Genre:
ISBN: 9789279283192

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A new evaluation of neutron induced reactions on 197Au nucleus in the energy regions below 500 eV and from 4 keV to 100 keV is presented. Complete evaluated data files in ENDF-6 format have been produced by joining the evaluation with corresponding files from the ENDF/B-VII. 1 library. The evaluation in the unresolved resonance region between 4 keV and 100 keV is based on a generalized single-level representation compatible with the energy-dependent option of the ENDF-6 format. The average partial cross sections have been expressed in terms of transmission coefficients by applying the Hauser-Feshbach statistical reaction theory including width fluctuations. The transmission coefficients have been obtained from a combined analysis of the capture cross section resulting from the cross section standards evaluation project and theoretical nonfluctuating cross sections derived from a dispersive coupled channel optical model. The evaluated cross sections have been validated by a comparison with transmission and capture data obtained at the time-of-flight facility GELINA. The evaluated files have been processed with the latest updates of NJOY. 99 to test their format and application consistency as well as to produce a continuous-energy data library in ACE format for use in Monte Carlo codes. The ACE files have been utilized to study the effect of the evaluated resonance parameters on results of lead slowing-down experiments. The evaluated files will be implemented in the next release of the JEFF-3 library which is maintained by the Nuclear Energy Agency of the OECD.