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Title: Determination of a deuteron-beryllium neutron source spectrum by multifoil activation

Abstract

The spectral neutron flux from a deuteron-beryllium neutron source, which is driven by a 19-MeV cyclotron deuteron beam and serves mainly for integral activation tests of fusion reactor structural materials, was determined by the multifoil activation method. Twenty-two selected threshold activation reactions were employed. An initial guess spectrum calculated by a Monte Carlo simulation was adjusted using the SAND-II code to be consistent with the measured reaction rates. The total neutron flux averaged over a 5 x 5 mm sample was found to be 2.52 {times} 10{sup 11} n/s{center_dot}cm{sup {minus}2} at 10 {micro}A of deuteron beam with uncertainty of {approximately}10%. The activation cross sections used were based on the FENDL/A-2.0 library. However, they were extrapolated beyond 20 MeV, the upper energy limit of that library, to the maximum neutron energy of 23.4 MeV and were modified where necessary. As a result, a self-consistent set of activation cross sections was obtained, which may also be used for the characterization of other neutron fields. The determined spectral neutron flux is to be used for analyses of integral activation tests of fusion reactor-relevant materials.

Authors:
;  [1]; ;  [2]
  1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)
  2. Forschungszentrum Karlsruhe (Germany). Inst. fuer Kern- and Energietechnik
Publication Date:
OSTI Identifier:
687461
Resource Type:
Journal Article
Journal Name:
Fusion Technology
Additional Journal Information:
Journal Volume: 36; Journal Issue: 2; Other Information: PBD: Sep 1999
Country of Publication:
United States
Language:
English
Subject:
07 ISOTOPE AND RADIATION SOURCE TECHNOLOGY; 70 PLASMA PHYSICS AND FUSION; NEUTRON SOURCES; NEUTRON SPECTRA; NEUTRON FLUX; THERMONUCLEAR REACTOR MATERIALS; NEUTRON ACTIVATION ANALYSIS; RADIOACTIVATION; DEUTERON BEAMS; BERYLLIUM; STRIPPING

Citation Formats

Maekawa, Fujio, Ikeda, Yujiro, Moellendorff, U. von, and Wilson, P.P.H. Determination of a deuteron-beryllium neutron source spectrum by multifoil activation. United States: N. p., 1999. Web.
Maekawa, Fujio, Ikeda, Yujiro, Moellendorff, U. von, & Wilson, P.P.H. Determination of a deuteron-beryllium neutron source spectrum by multifoil activation. United States.
Maekawa, Fujio, Ikeda, Yujiro, Moellendorff, U. von, and Wilson, P.P.H. Wed . "Determination of a deuteron-beryllium neutron source spectrum by multifoil activation". United States.
@article{osti_687461,
title = {Determination of a deuteron-beryllium neutron source spectrum by multifoil activation},
author = {Maekawa, Fujio and Ikeda, Yujiro and Moellendorff, U. von and Wilson, P.P.H.},
abstractNote = {The spectral neutron flux from a deuteron-beryllium neutron source, which is driven by a 19-MeV cyclotron deuteron beam and serves mainly for integral activation tests of fusion reactor structural materials, was determined by the multifoil activation method. Twenty-two selected threshold activation reactions were employed. An initial guess spectrum calculated by a Monte Carlo simulation was adjusted using the SAND-II code to be consistent with the measured reaction rates. The total neutron flux averaged over a 5 x 5 mm sample was found to be 2.52 {times} 10{sup 11} n/s{center_dot}cm{sup {minus}2} at 10 {micro}A of deuteron beam with uncertainty of {approximately}10%. The activation cross sections used were based on the FENDL/A-2.0 library. However, they were extrapolated beyond 20 MeV, the upper energy limit of that library, to the maximum neutron energy of 23.4 MeV and were modified where necessary. As a result, a self-consistent set of activation cross sections was obtained, which may also be used for the characterization of other neutron fields. The determined spectral neutron flux is to be used for analyses of integral activation tests of fusion reactor-relevant materials.},
doi = {},
journal = {Fusion Technology},
number = 2,
volume = 36,
place = {United States},
year = {1999},
month = {9}
}