Development of Neutronic and Thermal-Hydraulic Couple Code of AHRs and Preliminary Investigation on Bubble Distribution

The absence of radiolytic-gas bubbles strongly affects the steady operation of Aqueous Ho-mogeneous Reactors（AHRs）,and because of the buoyancy and collision effects,the bubble behavior and their steady distribution in the reactor is always hard to predict.Now,computation methods of AHRs always use a function to express the bubble distribution approximately.Related investigation shows that in CFX,using Multiple Size Group（MUSIG） model,the multi-phase simulation results predict the bubble behavior well,and tally with the experimental results of an AHR.This paper firstly introduces the neutronic and ther-mal-hydraulic couple code FMCAHR_CFX,and in the last chapter,FMCAHR_CFX is used for a preliminary analysis of a simple AHR.