MH-1A Core 3 Thermal Hydraulic Design Analysis.
ARMY ENGINEER REACTORS GROUP FORT BELVOIR VA ENGINEERING DIV
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A brief description of the MH-1A Floating Nuclear Power Plant is given, followed by the safety system setpoints and operating limits of the reactor. The safety criteria which form the basis for safe operation and protection of the core are presented. A parametric analysis is made of the thermal-hydraulic capabilities of the MH-1A Core 3 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 level startup, secondary system steam line rupture, and loss of reactor coolant flow. Author
- Nuclear Power Plants and Fission Reactor Engineering
- Fission Reactor Materials