An International Evaluation of the Neutron Cross Section Standards

    Volume 3, Issue 3 (March 2006)

    ISSN: 1546-962X

    CODEN: JAIOAD

    Published Online: 21 December 2005

    Page Count: 9


    Carlson, AD
    Physicist, National Institute of Standards and Technology, Gaithersburg, MD

    Badikov, SA
    Physicist, Institute of Physics & Power Engineering, Obninsk,

    Chen, Z
    Physicist, Tsinghua University, Beijing,

    Gai, EV
    Physicist, Institute of Physics & Power Engineering, Obninsk,

    Hale, GM
    Physicist, Los Alamos National Laboratory, Los Alamos, NM

    Hambsch, F-J
    Physicist, Institute for Reference Materials and Measurements, Geel,

    Hofmann, HM
    Physicist, Erlangen-Nürnberg University, Erlangen,

    Kawano, T
    Physicist, Los Alamos National Laboratory, Los Alamos, NM

    Larson, NM
    Physicist, Oak Ridge National Laboratory, Oak Ridge, TN

    Oh, S-Y
    Physicist, Korean Atomic Energy Research Institute, Yuseong, Daejeon,

    Pronyaev, VG
    Physicist, Institute of Physics & Power Engineering, Obninsk,

    Smith, DL
    Physicist, Argonne National Laboratory, Argonne, IL

    Tagesen, S
    Physicist, Vienna University, Vienna,

    Vonach, H
    Physicist, Vienna University, Vienna,

    (Received 20 June 2005; accepted 29 September 2005)

    Abstract

    Work is reported here on the process and present results of an international evaluation of the neutron cross section standards. The evaluations include the H(n,n), 3He(n,p), 6Li(n,t), 10B(n,α), 10B(n,α1γ), 197Au(n,γ), 235U(n,f), and 238U(n,f) standard reactions as well as the 238U(n,γ) and 239Pu(n,f) reactions. This evaluation was performed to include new experiments on the standards that have been made since the ENDF/B-VI evaluation was completed and to improve the evaluation process. Evaluations have been completed for the 6Li(n,t), 197Au(n,γ) and 238U(n,γ) cross sections. Also below 20 MeV the H(n,n), 235U(n,f), 238U(n,f) and 239Pu(n,f) cross sections are completed. Many of the cross sections being evaluated are used in neutron dosimetry for fluence determination. The general trend observed for the evaluations is an increase in the cross sections for most of the reactions from fractions of a percent to several percent compared with the ENDF/B-VI results.


    Paper ID: JAI13422

    DOI: 10.1520/JAI13422

    ASTM International is a member of CrossRef.

    Author
    Title An International Evaluation of the Neutron Cross Section Standards
    Symposium Reactor Dosimetry, 12th Volume, 2005-05-13
    Committee E10