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Neutron-source characterization and radiation-damage calculations for material studies [electronic resource].

Published
Argonne, Ill. : Argonne National Laboratory, 1981.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
Pages: 15 : digital, PDF file
Additional Creators
Argonne National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
In our quest to understand radiation damage in materials, it is vital that we characterize radiation sources in terms of neutron flux and spectra as well as the more-fundamental displacement damage, gas production, and transmutation rates. Such data are crucial to correlations of materials-property changes in different environments and to predictions of materials performance in inaccessible environments, such as fusion reactors. Dosimetry techniques have been developed to measure the neutron flux and spectra in diverse facilities including thermal, fast, and mixed reactors, T (d,n) and Be (d,n) accelerator sources, and high-energy spallation sources. Displacement-damage cross sections have been calculated for 36 elements spanning the periodic table. All of these exposure parameters can now be routinely measured with 10 to 15% relative accuracy at all existing radiation-effect facilities. 4 tables.
Report Numbers
E 1.99:conf-811145-16
conf-811145-16
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
11/09/1981.
"conf-811145-16"
"DE83007857"
International conference on neutron irradiation effects, Argonne, IL, USA, 9 Nov 1981.
Greenwood, L.R.
Funding Information
W-31-109-ENG-38
View MARC record | catkey: 14672024