Open AccessThermal and fission neutron flux measurements in process tubing and in neutron activation test locations
Author(s) -
R.W. Perkins
Publication year - 1961
Language(s) - English
Resource type - Reports
DOI - 10.2172/10124409
Subject(s) - neutron , neutron temperature , fission , neutron flux , radiochemistry , materials science , nuclear fission , neutron cross section , nuclear physics , neutron activation , fission products , nuclear engineering , chemistry , physics , engineering
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