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Calculation of absorbed dose from neutron irradiation by application of threshold-foil measurement data

Journal Article · · Annu. Book ASTM Stand.; (United States)
OSTI ID:5676293
The standard method outlines a procedure for calculating the absorbed dose in a material given the material composition, the neutron fluence, and threshold-foil data related to the neutron spectrum. The method is applicable to fast-pulsed reactors of the Godiva or TRIGA type, where a substantial fraction of the neutron fluence exceeds epithermal energies (that is, E > 0.01 MeV). A material exposed to the mixed neutron and gamma-ray radiation from such a reactor absorbs energy from both components. This method provides a procedure for calculating the neutron absorbed dose, and a companion standard, Method E 666, describes a technique for calculating the absorbed dose resulting from the gamma-ray component. The method is limited to materials for which tabulated kerma factors are available. (JMT)
OSTI ID:
5676293
Journal Information:
Annu. Book ASTM Stand.; (United States), Journal Name: Annu. Book ASTM Stand.; (United States) Vol. 45; ISSN ABASC
Country of Publication:
United States
Language:
English