Defect production efficiency in neutron-irradiated iron

Abderrafi M. Ougouag, Musa B. Danjaji, John G. Williams, James F. Stubbins, Mai A. Ghaly

Research output: Chapter in Book/Report/Conference proceedingConference contribution


Neutron cross sections have been calculated for total dpa production, stable defect production at low temperature, and for free defect production at high temperature. Calculations using the NJOY cross section processing code and ENDF/B-V cross sections were used to obtain displacement cross sections for neutron-irradiated iron. Published models of Simons and Wiedersich were used to obtain modified response functions for the production of stable defects at low temperature and for free defect survival, respectively. The effects of these different response functions on the energy ranges of significance in various neutron spectra and on the spectrum-averaged cross sections for these spectra have also been calculated.

Original languageEnglish (US)
Title of host publicationASTM Special Technical Publication
PublisherPubl by ASTM
Number of pages14
ISBN (Print)080311477X
StatePublished - 1992
Event15th International Symposium on Effects of Radiation on Materials - Nashville, TN, USA
Duration: Jun 19 1990Jun 21 1990

Publication series

NameASTM Special Technical Publication
ISSN (Print)0066-0558


Other15th International Symposium on Effects of Radiation on Materials
CityNashville, TN, USA

ASJC Scopus subject areas

  • Engineering(all)

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