抄録
Analytical models for the ATR are characterized for thermal hydraulics in a pressure tube, a steam drum and a water drum, based on the configuration features of the primary cooling system. PNC constructed the experimental facilities in 1970, simulating pressure tubes and fuel bundles in full scale to develop a thermal hydraulic code system. Typical models are explained for the thermal hydraulic analyses of the ATR under normal, operational transient and LOCA conditions.
