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Tuesday, July 21, 2020 | History

2 edition of Tables of evaluated neutron cross sections for fast reactor materials found in the catalog.

Tables of evaluated neutron cross sections for fast reactor materials

I. Langner

Tables of evaluated neutron cross sections for fast reactor materials

by I. Langner

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Published by Gesellschaft für Kernforschung m.b.H. in Karlsruhe .
Written in English

    Subjects:
  • Neutron cross sections -- Tables.

  • Edition Notes

    At head of title: Kernforschungszentrum Karlsruhe. Institut für Neutronenphysik und Reaktortechnik.

    Statementby I. Langner, J. J. Schmidt [and] D. Woll.
    ContributionsSchmidt, J. J. 1931- joint author., Woll, D., joint author., Kernforschungszentrum Karlsruhe. Institut für Neutronenphysik und Reaktortechnik.
    Classifications
    LC ClassificationsQC721 .L334
    The Physical Object
    Paginationxi, 663 p.
    Number of Pages663
    ID Numbers
    Open LibraryOL4640664M
    LC Control Number77472642

    In nuclear and particle physics, the concept of a neutron cross section is used to express the likelihood of interaction between an incident neutron and a target nucleus. In conjunction with the neutron flux, it enables the calculation of the reaction rate, for example to derive the thermal power of a nuclear power standard unit for measuring the cross section is the barn, which is. Reactor Dynamics. Reactor dynamics is the study of the time-dependence of the neutron flux, when the macroscopic cross sections are allowed to depend in turn on the neutron flux level. It is also referred to as reactor kinetics with feedbacks and with spatial effects.

    Neutron Fluence Calculation Methodology for Reactor Vessel APRZ-A-NRNP, Rev.0 KEPCO & KHNP ii Non-Proprietary REVISION HISTORY. @article{osti_, title = {Neutron Fission of ,,U and ,Pu: Cross Sections, Integral Cross Sections and Cross Sections on Excited States}, author = {Younes, W and Britt, H C}, abstractNote = {In a recent paper submitted to Phys. Rev. C they have presented estimates for (n,f) cross sections on a series of Thorium, Uranium and Plutonium isotopes over the range E{sub n} = .

    NEUTRON CAPTURE CROSS-SECTIONS NEUTRON ACTIVATION occurs as a result of interaction between incident neutron and target nucleus of an atom. The radius of a typical atom is of the order of m; that of a nucleus is of m; and that of neutron is of m. The probability that such an interaction to take place, for a. KEYWORDS: uranium , neutron capture cross section, fast reactor, nuclear characteristics, JENDL, least-squares method, BFS, sensitivity coefficients I. Introduction The latest version of the Japanese Evaluated Nuclear Data Library (JENDL)1) was released in May, Numer-ous integral tests for this version have been carried out for.


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Tables of evaluated neutron cross sections for fast reactor materials by I. Langner Download PDF EPUB FB2

Get this from a library. Tables of evaluated neutron cross sections for fast reactor materials. [I Langner; J J Schmidt; D Woll; Kernforschungszentrum Karlsruhe. Institut für. Atlas of Neutron Capture Cross Sections The NGATLAS contains neutron capture cross sections in the range eV - 20MeV as evaluated and compiled in recent activation libraries.

Numerical values of (n,g) cross sections are available for a total of targets for the elements H (Z=1, A=1) to Cm (Z=96, A=) totaling reactions.

ADS-ACE: Contains pointwise continuous-energy cross-section data in ACE format for MCNP calculations; also includes probability tables (PT) in the unresolved resonance range, if applicable. ADS-MATXS: Contains multigroup cross-section data in MATXS format. Data are available for 30 materials relevant for ADS benchmarking.

Neutron cross sections for fast reactor materials. Karlsruhe, Gesellschaft für Kernforschung m.b.H., [v. 1, ] (OCoLC) Document Type: Book: All Authors / Contributors: J J Schmidt; Kernforschungszentrum Karlsruhe. Institut für Neutronenphysik und Reaktortechnik. Click here to buy a book, photographic periodic table poster, card deck, or 3D print based on the images you see here.

Common Properties Abundance in Earth's Crust. The ECCO/ERANOS code package contains several neutron cross section libraries, all derived from the JEF nuclear data evaluated files [5]. These include. Nuclear Data for Science and Technology The Taco Experiment for the Determination of Integral Neutron Cross-Sections in a Fast Reactor.

Cricchio, R. Ernstberger, L. Koch, R. Wellum Neutron Cross Section Evaluation for Am, Am, Am. The Handbook of Nuclear Engineering is an authoritative compilation of information regarding methods and data used in all phases of nuclear engineering.

Addressing nuclear engineers and scientists at all academic levels, this five volume set provides the latest findings in nuclear data and experimental techniques, reactor physics, kinetics, dynamics and control.

Neutron scattering lengths and cross sections. NOTE: The above are only thermal neutron cross sections. I do not have any energy dependent cross sections.

For energy dependent cross sections please go to the National Nuclear Data Center at Brookhaven National Lab. Select the element, and you will get a list of scattering lengths and cross sections.

G-factors of JENDL cross sections are given in cross section tables. /02/06 Atomic mass data were replaced with recommendation of Audi et al.

[The Ame atomic mass evaluation (II) bya and lt, Nuclear Physics A p ()]. Spin and half-lives were replaced with the data of WWW Chart of the Nuclides. The possibility of nuclear reactions is measured for each isotope, and given as “cross section” which is evaluated and listed in the nuclear data libraries such as JENDL [1] or ENDF [2].

Cross sections of each isotope, not atom, depend on energy of neutrons. It is noted that “transmutation” effects are permanent effects on materials. Neutron Cross Sections presents the principles of cross-section measurement and use, as well as sufficient theory so that the general behavior of cross sections is made understandable.

This compilation is a direct result of experiences connected with the collection and evaluation of cross-section data during the past eight years at ""Sigma.

Nuclear Fission and Neutron-Induced Fission Cross-Sections is the first volume in a series on Neutron Physics and Nuclear Data in Science and Technology.

This volume serves the purpose of providing a thorough description of the many facets of neutron physics in different fields of nuclear applications.

A re-evaluation of all thermal neutron cross sections and neutron resonance integrals has been performed, utilizing the previous database of the ``Barn Book`` and all of the more recently published experiments.

Only significant changes or previously undetermined values are recorded in this report. The source for each value is also recorded in the accompanying table. Tables of cross sections for fast neutron reactions Unknown Binding – January 1, by Texas Nuclear Corporation (Author) See all formats and editions Hide other formats and editions.

Enter your mobile number or email address below and we'll send you a link to download the free Kindle App. Author: Texas Nuclear Corporation. 94 Pu fission cross-section is barns 10 5 B boron, graphite contaminant, boronated water used for control 54 Xe × fission product, “poison”, can cause restart problems (slow creation) Cd at eV resonance peak, used in control rods Neutron absorption cross-sections of important nuclides.

tions. Kerma factors calculated from the evaluated cross sections were also compared with measurements and other evaluations. KEYWORDS: neutron nuclear data, data analysis, evaluation, car MeV rangeneutron cross sections, total cross sections, elastic cross sections, inelastic cross.

List of Tables xviii. List of Figures xix. 1 Nuclear Power Plants 1. 2 Neutronnucleus Reaction and Neutron Cross Section 3 Neutron Flux, Reaction Rate, and Effective Cross Section 4 Derivation of the Neutron Diffusion Equation 5 Applications of the One-Group Neutron Diffusion Equation 6 Numerical Solution of the Neutron.

A fast-neutron reactor or simply a fast reactor is a category of nuclear reactor in which the fission chain reaction is sustained by fast neutrons, as opposed to thermal neutrons used in thermal-neutron reactors.

Such a reactor needs no neutron moderator, but requires fuel that is relatively rich in fissile material when compared to that required for a thermal-neutron reactor.

Multigroup Neutron Cross Section Data Tables Based upon ENDF/B-VII.1}, author = {Conlin, Jeremy Lloyd and Parsons, Donald Kent and Gardiner, Steven J.

and Gray, Mark Girard and Lee, Mary Beth and White, Morgan Curtis}, abstractNote = {A new multi-group neutron cross section library has been released along with the release of NDI version. The core characteristics have been evaluated with a continuous-energy model Monte Carlo code MVP and the JENDL cross-section library.

The result indicates that the discharged fuel burn-up can be increased by about 7% relative to that of no moderator in the blanket region due to the power flattening when the number of deuteride.Neutron Absorption Cross-section.

The likelihood of a neutron absorption is represented by the absorption cross section as σ a. The relative likelihoods of an absorption reaction or a neutron scattering are represented by dividing the total cross section into scattering and absorption cross sections: σ t = σ s + σ a.NUCLEAR CROSS SECTIONS AND NEUTRON FLUX Reactor Theory (Neutron Characteristics) NP Page 8 Rev.

0 Whether a neutron will interact with a certain volume of material depends not only on the microscopic cross section of the individual nuclei but also on the number of nuclei within that volume.