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NRC adopts ROP updates
The Nuclear Regulatory Commission has approved a significant overhaul of its Reactor Oversight Process (ROP) baseline inspection program that stresses a leaner, more risk-focused inspection process.
This adoption comes just over a month after NRC officials published their findings on the proposed ROP changes. The changes would reduce the number of hours spent annually on direct inspections at U.S. nuclear power plants by 38 percent.
O. E. Dwyer
Nuclear Science and Engineering | Volume 15 | Number 1 | January 1963 | Pages 52-57
Technical Paper | doi.org/10.13182/NSE63-A26263
Articles are hosted by Taylor and Francis Online.
Theoretical equations have been derived for calculating heat transfer coefficients for a fluid flowing through a concentric annulus for the following two cases: (A) constant and equal heat fluxes from both walls, and (B) constant, but unequal, heat fluxes from the walls, with equal wall temperatures at a given axial position along an annular channel. In the derivations, the conditions of fully-established velocity and temperature profiles, and independence of physical properties with temperature variation across the flow channel, were assumed. The only geometrical parameter in this general case is the radius ratio r2/r1, and in the study it was varied from 1.0 to 10.0.