FUNCTIONAL PERFORMANCE OF THE HELICAL COIL STEAM GENERATOR CONSOLIDATED NUCLEAR STEAM GENERATOR (CNSG) IV SYSTEM
The objective of this project was to study the functional performance of the CNSG - IV helical steam generator to demonstrate that the generator meets steady-state and transient thermal-hydraulic performance specifications and that secondary flow instability will not be a problem. Economic success of the CNSG concepts depends to a great extent on minimizing the size of the steam generator and the reactor vessel for ship installation. Also, for marine application the system must meet stringent specifications for operating stability, transient response, and control. The full-size two-tube experimental unit differed from the CNSG only in the number of tubes and the mode of primary flow. In general, the functional performance tests demonstrated that the helical steam generator concept will exceed the specified superheat of 35F at 100% load. The experimental measured superheat at comparable operating conditions was 95F. Testing also revealed that available computer codes accurately predict trends and overall performance characteristics.
- An executive summary report. See also report PB-253324.
Babcock and Wilcox CompanyResearch Center, P.O. Box 835
Alliance, OH United States 44601
- Watson, G B
- Publication Date: 1975-12
- Pagination: 58 p.
- TRT Terms: Economics; Equipment tests; Nuclear power; Nuclear power generation; Nuclear reactors
- Old TRIS Terms: Consolidated nuclear steam generators; Nuclear reactor testing
- Subject Areas: Economics; Marine Transportation; Vehicles and Equipment;
- Accession Number: 00141217
- Record Type: Publication
- Source Agency: National Technical Information Service
- Report/Paper Numbers: ARC-5178-ES, MA/RD-920-76018-ES
- Contract Numbers: MARAD-1-35555
- Files: TRIS
- Created Date: Oct 26 1976 12:00AM