LYNX1: reactor fuel assembly thermal hydraulic analysis code

LYNX1 is a FORTRAN IV program written for the CDC 7600 computer system at Babcock and Wilcox's Nuclear Power Generation Division in Lynchburg, Virginia. The program performs the steady-state thermal and hydraulic analysis of the reactor core coolant by solving the basic conservation equations. Each fuel assembly is taken as a unit in the reactor cross-sectional plane, and the core is divided into a finite number of axial increments. By using an iterative solution method, the program is capable of determining the inlet pressure profile of the reactor core with a given inlet velocity profile. The boundary condition of a known exit pressure profile is used in the solution. The program is also capable of determining the inlet velocity profile of the core with a given inlet pressure profile at the same boundary condition. The calculation can be made at full reactor thermal input or any fraction thereof. Inter-bundle diversion crossflow is accounted for in the analysis