THERMO-HYDRAULIC STEADY-STATE ANALYSIS OF THE NS SAVANNAH
A thermo-hydraulic steady-state analysis of the N.S. Savannah General Electric replacement reactor core is presented. Results are summarized in terms of channel and subchannel geometry, values of coolant flow rate, mass velocity, enthalpy rise, temperature rise, minimum burnout margin, and location of minimum local burnout margin. Detailed analyses and sample calculations are given for: locating the worst subchannel for burnout; coolant flow rates; actual local heat flux axial distribution; channel and subchannel rise of enthalpy; local burn-out heat flux axial distribution; local burn-out margin axial distribution; power level causing burnout; fuel time constants during a transient warmup period; and coolant flow rate through control rod channels.
- This document is available for review at the Department of Commerce Library, Main Commerce Building, Washington, D.C., under reference number GEAP-3244.
General ElectricMarine Turbine & Gear Engineer, 1100 Western Ave
Lynn, MA USA 01910
- Blair, P M
- Publication Date: 1959-9-10
- Features: Figures; References; Tables;
- Pagination: 37 p.
- TRT Terms: Design; Heat transfer; Nuclear powered ships; Nuclear reactor coolants; Nuclear reactor cores
- Uncontrolled Terms: Design criteria
- Subject Areas: Design; Marine Transportation; Vehicles and Equipment;
- Accession Number: 00026197
- Record Type: Publication
- Source Agency: Maritime Administration
- Report/Paper Numbers: GEAP-3244
- Contract Numbers: AT(04-3)-189
- Files: TRIS, USDOT
- Created Date: Apr 13 1973 12:00AM