Mh-1A Steady State and Transient Thermal-Hydraulic Design Analysis

摘要

A brief description of the MH-1A floating nuclear power plant is given followed by the safety system set points and operating limits of the reactor. The design bases, from which the limits were developed, are given. A parametric analysis is made of the thermal-hydraulic capabilities of the MH-1A Type I core during steady-state operation. This includes calculation of peak centerline fuel temperatures at various powers, the maximum linear heat rate, DNBR, and maximum hot channel enthalpy rise. Also included are analyses of transient conditions accompanying such accidents as power range rod withdrawal and main steam pipe rupture. (Author)