Fuel Management and Fuel Performance at Point Lepreau NGS

Abstract

Fuel management strategy and excess reactivity targets for the Point Lepreau Nuclear Generating Station are presented. Attained discharge burnup and peak channel power are compared to design targets. Based on the commissioning experience of 3-D diffusion depletion code RFSP, we now use instantaneous device positions and distributed xenon options to compute flux and burnup increment. Limitations of flux mapping-based PMCR code are discussed. Due to these limitations instantaneous RFSP simulations are now used to compute ripple used


in routine ROP detector calibration. Systems used to identify, locate and confirm defective fuel are discussed. A summary of fuel performance at PLGS for fuel manufactured by different manufacturers for the period 1982 to 1986 is presented.