Modeling a Helical-coil Steam Generator in RELAP5-3D for the Next Generation Nuclear Plant

Technical Report · Sat Jan 01 04:00:00 EST 2011

DOI:https://doi.org/10.2172/1004263· OSTI ID:1004263

Hoffer, Nathan V.; Sabharwall, Piyush; Anderson, Nolan A.

Options for the primary heat transport loop heat exchangers for the Next Generation Nuclear Plant are currently being evaluated. A helical-coil steam generator is one heat exchanger design under consideration. Safety is an integral part of the helical-coil steam generator evaluation. Transient analysis plays a key role in evaluation of the steam generators safety. Using RELAP5-3D to model the helical-coil steam generator, a loss of pressure in the primary side of the steam generator is simulated. This report details the development of the steam generator model, the loss of pressure transient, and the response of the steam generator primary and secondary systems to the loss of primary pressure. Back ground on High Temperature Gas-cooled reactors, steam generators, the Next Generation Nuclear Plant is provided to increase the readers understanding of the material presented.

• Research Organization: Idaho National Laboratory (INL)
• Sponsoring Organization: DOE - NE
• DOE Contract Number: AC07-05ID14517
• OSTI ID: 1004263
• Report Number(s): INL/EXT-10-19621
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
DESIGN
EVALUATION
HEAT EXCHANGERS
NGNP
SAFETY
SIMULATION
STEAM GENERATORS
TRANSIENTS
TRANSPORT