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Goland, A.N.; Parkin, D.M.
Proceedings of the 1. ASTM-EURATOM symposium on reactor dosimetry. Petten, Holland, September 22-26, 19751977
Proceedings of the 1. ASTM-EURATOM symposium on reactor dosimetry. Petten, Holland, September 22-26, 19751977
AbstractAbstract
[en] The characteristics of defect production in neutron spectra can be determined by utilizing neutron cross section data (e.g. ENDF/B), detailed neutron spectral data and radiation damage models. The combination of neutron cross section and spectral data is a fundamental starting point in applying damage models. Calculations using these data and damage models show that there are significant differences in the way defects are produced in various neutron spectra. Nonelastic events dominate the recoil energy distribution in high-energy neutron sources such as those based upon fusion and deuteron-breakup reactions. Therefore, high-energy neutron cross sections must be measured or calculated to supplement existing data files. Radiation damage models can then be used to further characterize the diverse neutron spectra
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Commission of the European Communities, Petten (Netherlands). Joint Nuclear Research Center; p. 12-22; 1977; p. 12-22; 1. International symposium on reactor dosimetry: developments and standardization; Petten, Netherlands; 22 - 26 Sep 1975
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