SYMPOSIA PAPER Published: 01 January 1970
STP28629S

Chapter 5—Neutron Dosimetry and Spectrum

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Both neutron dosimetry and neutron spectrum have been referred to extensively throughout this report. They are of equal importance with mechanical property changes since the changes would be essentially meaningless without the point of reference provided by dosimetry and spectrum. Just as creep rupture studies have an accurate time base and carefully documented environments, so must radiation effects studies have accurate neutron dosimetry for a base and accurate spectral analysis for environmental definition. Furthermore, a very important requisite for both fluence measurements and spectral definition is a damage model which relates experimentally measured values to real physical conditions in the reactor. Therefore, damage model considerations will be carried along throughout the discussion of the two principal subjects, dosimetry and spectrum.

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Developed by Committee: E10
Pages: 207–235
DOI: 10.1520/STP28629S
ISBN-EB: 978-0-8031-4592-4
ISBN-13: 978-0-8031-0276-7