Methods for steady state thermal-hydraulic analysis of pressurized water reactor cores

Abstract

A one-pass simplified analysis method for steady state PWR core has been developed. The advantages over the other multistage approaches have been discussed and compared- Recommended nodal patterns for modelling the reactor core have been proposed. Also the effect due to the lumped channel technique utilized in both the simplified method and existing multistage methods has been investigated for both D and 3D problems. For the nodal pattern recommended with the proposed one-pass analysis method, use of the lumped channel technique introduces negligible errors.