A model of the imaging process in neutron radiography has been employed to determine the edge-spread function for a given radiographic system. As an aid to the numerical evaluation of this function, approximate analytical representations of the resolution function have been examined. This has facilitated the formulation of an analytical technique for determining the effects of neutron beam divergence. Comparisons are presented between computational results and a series of experiments designed to test the validity of the theoretical model. The agreement obtained is very satisfactory.

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NG CANDU is the “Next Generation” CANDU® reactor, aimed at producing electrical power at a capital cost significantly less than that of the current reactor designs. A key element of cost reduction is the use of H2O as coolant and Slightly Enriched Uranium fuel in a tight D2O-moderated lattice. The innovations in the CANDU core physics result in substantial improvements in economics as well as significant enhancements in reactor licensability, controllability, and waste reduction. The full-core coolant-void reactivity in NG CANDU is about −3 mk. Power coefficient is substantially negative. Fuel burnup is about three times the current natural-uranium burnup.