Thermal Hydraulic Analysis of MH-1A Core 5
Abstract
This report presents the thermal hydraulic analysis of Core 5 for the MH-1A Floating Barge Nuclear Power Plant. The primary purpose of this study is to demonstrate that the reactor core is capable of meeting normal steady-state and transient performance requirements without violating the integrity of the fuel-element cladding. The analyses presented herein define the limits of safe operation for the core in terms of measurable reactor parameters: Reactor power, primary system pressure, coolant temperature and flow. The reactor protection system is designed to trip the reactor to protect the core in the event that reactor parameters approach the core design limits. The steady-state thermal analysis shows that the prescribed setpoints with allowance for error assure protection during all normal operations. The analysis of limiting reactor transients caused by operator error or equipment malfunction demonstrates the adequacy of the protection system in assuring that core limits are not exceeded during anticipated transient conditions.
Document Details
- Document Type
- Technical Report
- Publication Date
- May 01, 1974
- Accession Number
- ADA012148
Entities
People
- Henry C. Gignilliat
- Peter E. Francisco
- Randal M. Devault
- Thomas M. Rotchford