Abstract
Digital computer Program K constructs the two energy-group analysis of a cylindrical reactor core with an off-center control red. Solutions are constructed for the fast and slow neutron flux in terms of red-centered cylindrical coordinates and also in terms of corecentered cylindrtcal coordinates. The effect of the control rod is expressed in terms of fast and slow albedos at the rod-core interface. The boundary conditions at the core outer surface are expressed in terms of energyaveraged flux logarithmic derivatives at the radial core reflector interface and at the end core reflector interfaces. Program K calculates the reactivity worth of the off-center control rod, calculates fast flux, slow flux, and relative power density at red-centered and corecentered mesh points, and produces cathode-ray-tube plots of fast flux and/or slow flux and/or relattve power density versus radius or angle in either the redcentered or the core-centered coordinate system. The input for Program K consists of geometric and physical parameters for the control rod and reactor core, data spectfying rod- centered and core-centered mesh points, and data specifying the CRT plots desired. The physics and mathematics of the problem, the numerical analysis used in formulating the program computations, and the program are discussed. (auth)
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