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New unfolding code for a multisphere neutron spectrometer

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5737263

Accurate measurements of neutron doses in the containment of a commercial nuclear power plant have been a concern in the last several years. If neutron dosimeters are used to assess exposures in a spectral environment substantially different from that in which they were calibrated, the dose equivalent interpretation of these dosimeters can be an order of magnitude higher than the actual dose. Proper characterization of the spectral environment will provide proper corrections for the reading. Many computer programs have been written for unfolding the spectrum with the measured count rates. A new unfolding computer code has been devised based on the response function calculated from a neutron transport code for 25 neutron energy groups from thermal to 15 MeV.

Research Organization:
Univ. of Missouri, Columbia
OSTI ID:
5737263
Report Number(s):
CONF-851115-
Journal Information:
Trans. Am. Nucl. Soc.; (United States), Journal Name: Trans. Am. Nucl. Soc.; (United States) Vol. 50; ISSN TANSA
Country of Publication:
United States
Language:
English