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Calculations Of Neutron Damage Cross Sections In Silicon Gallium Arsenide And Iron
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Book Synopsis Calculations of Neutron Damage Cross Sections in Silicon, Gallium Arsenide and Iron by : Musa Babar Danjaji
Download or read book Calculations of Neutron Damage Cross Sections in Silicon, Gallium Arsenide and Iron written by Musa Babar Danjaji and published by . This book was released on 1993 with total page 320 pages. Available in PDF, EPUB and Kindle. Book excerpt: The neutron cross-section processing code NJOY has been modified to calculate total displacements kerma cross-sections for silicon, gallium, arsenic and gallium arsenide. The modified NJOY is also used to calculate the displacement cross-sections for iron. NJOY was further modified to calculate partially integrated differential displacements kerma cross-sections or displacement kerma matrix elements for neutron interaction in Si and GaAs. The theory behind the calculation of the displacement kerma matrix is also extended to calculate the displacement per atom (dpa) cross-sections for production of displacements in cascades of specific size ranges in iron. Published models of Simons and Wiedersich were used to obtain modified response functions for the production of stable defects at low temperature and for free defect survival, respectively, in iron. The effects of these different response functions on the energy ranges of significance in various neutron spectra have also been calculated. The displacement energy calculated by the Monte-Carlo code MARLOWE is used to adjust the displacement energy calculated by the Lindhard partition function in NJOY for silicon and iron.
Book Synopsis Burst Generation Rates in Silicon and Gallium Arsenide from Neutron-Induced Nuclear Recoils by : John R. Letaw
Download or read book Burst Generation Rates in Silicon and Gallium Arsenide from Neutron-Induced Nuclear Recoils written by John R. Letaw and published by . This book was released on 1987 with total page 40 pages. Available in PDF, EPUB and Kindle. Book excerpt: The HETC code (Los Alamos National Laboratory version) is used to estimate the energy spectra of residual nuclei in n-Si and n-GaAs reactions between 50 MeV and 1 GeV. A computation of the components of the burst generation rate from neutron-induced nuclear recoils between 1 MeV and 1 GeV is based on the Monte Carlo results and measured cross sections. These data may be applied to the compution of single-event upset rates from high-energy neutrons in the atmosphere and in spacecraft. (RH).
Book Synopsis Comparison of Neutron and Gamma Radiation Damage in Semiconductors by : M. N. Robinson
Download or read book Comparison of Neutron and Gamma Radiation Damage in Semiconductors written by M. N. Robinson and published by . This book was released on 1965 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Neutron Displacement Damage Cross Sections for Structural Metals by : DG. Doran
Download or read book Neutron Displacement Damage Cross Sections for Structural Metals written by DG. Doran and published by . This book was released on 1976 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiation test data on reactor structural materials should include, in addition to fluence, the displacing dose expressed as displacements per atom (dpa) or damage energy per atom (depa). This provides a spectrum-dependent parameter that serves as a starting point for data correlations, as well as an exposure unit that is common to both neutron and charged-particle irradiations. To make this possible, displacement damage cross sections for neutrons have been calculated for aluminum, vanadium, chromium, iron, nickel, copper, zirconium, columbium, molybdenum, tantalum, tungsten, lead, and stainless steel using evaluated nuclear data files (ENDF/B-IV) data and the Lindhard energy partition model. These data extend to 20 MeV, hence cover the energy ranges of primary interest for both fission and fusion reactor applications. Tables are given in a standardized energy group structure. Figures are included to show the relative contributions of the various neutron scattering processes to both the primary knock-on atom spectra and the damage cross sections. A brief description of calculational procedures is given.
Book Synopsis Neutron-induced Gamma-ray Production Cross Sections for Silicon and Tungsten by : W. E. Tucker
Download or read book Neutron-induced Gamma-ray Production Cross Sections for Silicon and Tungsten written by W. E. Tucker and published by . This book was released on 1969 with total page 122 pages. Available in PDF, EPUB and Kindle. Book excerpt: Experimental measurements of the differential cross sections for the production of gamma rays in natural silicon and tungsten in the energy range from 5.0 to 11.0 MeV are presented. Theoretical calculations of the production cross sections for silicon, based on statistical theory and the Satchler formalism, with modifications by Moldauer, have been made, and comparisons of these calculations and other nuclear model calculations with experiment are discussed.
Book Synopsis Fast Neutron Cross Sections of Iron, Silicon, Aluminum, and Oxygen by : E. S. TROUBETZKOY
Download or read book Fast Neutron Cross Sections of Iron, Silicon, Aluminum, and Oxygen written by E. S. TROUBETZKOY and published by . This book was released on 1959 with total page 53 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Neutron and Gamma Ray Production by :
Download or read book Neutron and Gamma Ray Production written by and published by . This book was released on 1973 with total page 64 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Displacement Damage in Silicon Irradiated with 6- to 10-MeV Neutrons by : J. E. Youngblood
Download or read book Displacement Damage in Silicon Irradiated with 6- to 10-MeV Neutrons written by J. E. Youngblood and published by . This book was released on 1977 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt: Some preliminary experimental and theoretical results on the energy dependence of neutron-induced displacement damage in silicon are presented. The reduction in carrier lifetime, as reflected in the change in forward voltage at a fixed injection level, has been measured in wide-base silicon diodes, for monoenergetic neutrons at selected energies between 5.6 and 9.8 MeV. Twenty-five measurements at 19 energies were made. To calculate the variations in damage with neutron energy, a computer program that could utilize all details of the best available neutron cross section data was prepared. This program accepts coefficients for a Legendre polynomial fit of a partial cross section, determines the silicon recoil energy at a particular angle, and calculates the Lindhard fraction of energy for displacement damage. The calculated results provide a direct indication of the effect of angular distributions and the sensitivity of damage calculations to various details of the input neutron cross sections. (Author).
Book Synopsis Calculation of Neutron Cross Sections on Iron Up to 40 MeV. by :
Download or read book Calculation of Neutron Cross Sections on Iron Up to 40 MeV. written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The development of high energy d + Li neutron sources for fusion materials radiation damage studies will require neutron cross sections up to 40 MeV. Experimental data above 15 MeV are generally sparse or nonexistent, and reliance must be placed upon nuclear-model calculations to produce the needed cross sections. To satisfy such requirements for the Fusion Materials Irradiation Test Facility (FMIT), neutron cross sections have been calculated for 54 56Fe between 3 and 40 MeV. These results were joined to the existing ENDF/B-V evaluation below 3 MeV. In this energy range, most neutron reactions can be described using the Hauser-Feshbach statistical model with corrections for preequilibrium and direct-reaction effects. To properly use these models to obtain realistic cross sections, emphasis must be placed upon the determination of suitable input parameters (optical model sets, gamma-ray strength functions, level densities) valid over the energy range of the calculation. To do this, several types of independent data were used to arrive at consistent parameter sets as described.
Book Synopsis Calculation of Neutron Cross Sections on Iron Between 3 and 40 MeV. [Hauser-Feshbach Model]. by :
Download or read book Calculation of Neutron Cross Sections on Iron Between 3 and 40 MeV. [Hauser-Feshbach Model]. written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The use of high energy d+Li sources to produce neutrons for radiation damage studies will require evaluated neutron cross sections up to energies of 40 MeV. Experimental data in this energy region are scarce, and reliance must be placed upon nuclear model calculations to provide the necessary cross sections. We have thus calculated neutron-induced cross sections on 54Fe and 56Fe between 3 and 40 MeV using the multistep preequilibrium Hauser-Feshbach model code GNASH. Special care was taken in the determination of optical model parameters applicable over this wide energy range through use of, and comparison to, neutron total cross section and elastic angular distribution data, (p, n), and (.cap alpha., n) data, as well as other high energy proton induced reaction cross sections and spectral results. The preequilibrium-statistical calculations using these parameters as well as gamma-ray strength functions, level densities, and discrete level information reproduce well most available experimental measurements above 3 MeV for varied reaction types including gamma-ray production data. 12 references.
Book Synopsis Dissertation Abstracts International by :
Download or read book Dissertation Abstracts International written by and published by . This book was released on 1993-07 with total page 754 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Neutron and Gamma Ray Production Cross Sections for Silicon by : M.R. Bhat
Download or read book Neutron and Gamma Ray Production Cross Sections for Silicon written by M.R. Bhat and published by . This book was released on 1973 with total page 51 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book SPECTER written by and published by . This book was released on 1985 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Neutron displacement damage-energy cross sections have been calculated for 41 isotopes in the energy range from 10−1° to 20 MeV. Calculations were performed on a 100-point energy grid using nuclear cross sections from ENDF/B-V and the DISCS computer code. Elastic scattering is treated exactly including angular distributions from ENDF/B-V. Inelastic scattering calculations consider both discrete and continuous nuclear level distributions. Multiple (n, xn) reactions use a Monte Carlo technique to derive the recoil distributions. The (n, d) and (n, t) reactions are treated as (n, p) and (n, 3He) as (n, 4He). The (n, .gamma.) reaction and subsequent .beta.-decay are also included, using a new treatment of .gamma.-.gamma. coincidences, angular correlations, .beta.-neutrino correlations, and the incident neutron energy. The Lindhard model was used to compute the energy available for nuclear displacement at each recoil energy. The SPECTER computer code has been developed to simplify damage calculations. The user need only specify a neutron energy spectrum. SPECTER will then calculate spectral-averaged displacements, recoil spectra, gas production, and total damage energy (Kerma). The SPECTER computer code package is readily accessible to the fusion community via the National Magnetic Fusion Energy Computer Center (NMFECC) at Lawrence Livermore National laboratory.
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1976 with total page 1118 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fluctuations in the Neutron Cross Sections of Silicon by : Steven Munroe Grimes
Download or read book Fluctuations in the Neutron Cross Sections of Silicon written by Steven Munroe Grimes and published by . This book was released on 1968 with total page 274 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Spallation Radiation Damage Calculations and Database by : Monroe S. Wechsler
Download or read book Spallation Radiation Damage Calculations and Database written by Monroe S. Wechsler and published by . This book was released on 2006 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: A radiation damage database at NCSU is described that contains, at present, cross sections for damage energy, displacements, helium, and hydrogen. For neutrons and protons at 20-3200 MeV energies, the targets include 23 target elements from Mg to U and eight practical alloys. The underlying calculations employ Bertini, ISABEL, and CEM2k intranuclear cascade models as provided within MCNPX, three level-density formulations (GCCI, HETC, and Jülich), and multistage pre-equilibrium model (MPM) on and off. The database also includes radiation damage cross sections for lower-energy neutrons and protons, as obtained from LA150, SPECTER, ENDF, and SRIM. Examples of the database contents are provided with regard to damage energy and displacement cross sections for neutrons on Al, Fe, and W. Also, neutron flux and displacement rate calculations are described for neutrons on Fe and the 316 stainless steel mercury container vessel at SNS. In addition, discrepancies between the codes are discussed.
Book Synopsis Scientific and Technical Aerospace Reports by :
Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1995 with total page 704 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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