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Neutron Dosimetry for Fast-Reactor Irradiation and Surveillance Testing Pages: 10 Published: Jan 1969
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View License Agreement Source: STP457-EB Abstract Dosimetry for fast-reactor irradiation experiments introduces problems not encountered in thermal reactors. The difference in neutron spectrum causes quite different responses among candidate dosimetry materials. Moreover, the damage modes in fast-reactor irradiations and in thermal reactor irradiations may be quite different. This work is aimed at developing adequate methods for spectral determinations, neutron dosimetry, and damage correlation for fast-reactor tests. Spectral determinations have been performed using a multiple foil activation technique (SAND-II). The SAND-II analysis provides integral neutron flux data with an absolute accuracy of 10 to 30 percent. Intercomparison of analytical results, neutron spectrometer results, and SAND-II determinations indicate reasonable agreement among all three techniques. While the SAND-II technique provides fluence data, threshold and resonance monitors are simpler to use. A slight modification of monitoring procedures used in thermal reactors suffices for fast-reactor dosimetry. Results from activation monitors in EBR-II and ECEL indicate the feasibility of the monitoring methods. Damage correlation techniques depend on the mechanisms causing damage. Two of the mechanisms causing property changes during fast-reactor irradiations are displacement production and helium generation by neutron reactions. The fluence dependence for these mechanisms illustrate the need for correlation analyses. Keywords: radiation effects, neutrons, irradiations, reactors, neutron dosimetry, neutron spectra, tests, evaluation Paper ID: STP41856S Committee/Subcommittee: E10.08 DOI: 10.1520/STP41856S ASTM International is a member of CrossRef. | ||