Accelerated materials evaluation for nuclear applications

作者:Griffiths M*; Walters L; Greenwood L R; Garner F A
来源:Journal of Nuclear Materials, 2017, 488: 46-62.
DOI:10.1016/j.jnucmat.2017.02.039

摘要

This paper addresses the opportunities and complexities of using materials test reactors with high neutron fluxes to perform accelerated studies of material aging in power reactors operating at lower neutron fluxes and with different neutron flux spectra. Radiation damage and gas production in different reactors have been compared using the code, SPECTER. This code provides a common standard from which to compare neutron damage data generated by different research groups using a variety of reactors.

  • 出版日期2017-5