SM-1 Core III Thermal Hydraulic Analysis,
Abstract
A brief description of the SM-1 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 SM-1 Core III during steady-state operation. This includes calculation of peak centerline fuel temperatures at various powers, minimum DNBR, and maximum hot channel enthalpy rise. Also included are analyses of transient conditions accompanying uncontrolled rod withdrawal in the power range and during source level startup, secondary system steam line rupture, and loss of reactor coolant flow. (Author)
Document Details
- Document Type
- Technical Report
- Publication Date
- Sep 14, 1971
- Accession Number
- AD0730929
Entities
People
- Henry C. Gignilliat
- James D. Franson
- Paul M. Terpolilli