Thermal Hydraulic Analysis of MH-1A Core 4
Abstract
Steady-state and transient thermal analyses of the MH-1A Floating Nuclear Power Plant, Core 4 are presented for normal operation and anticipated transients. The reactor core safety limits which form the basis for safe operation and core protection are established in terms of measurable reactor parameters. The ability of the reactor protection system to prevent violation of the core safety limits is demonstrated. The steady-state analysis includes an evaluation of the fuel and clad temperature distribution and the limiting heat flux and coolant enthalpy conditions. Also presented are analyses of limiting reactor transients including uncontrolled rod withdrawal in the power range and during source level startup, secondary system steam line rupture, and loss of reactor coolant flow due to loss of power to both pumps.
Document Details
- Document Type
- Technical Report
- Publication Date
- Jul 20, 1972
- Accession Number
- AD0748831
Entities
People
- Henry C. Gignilliat
- James W. Iii Wagoner
- Randall M. Devault