MINET simulation of a helical coil sodium/water steam generator, including structural effects

Technical Report · Sun Apr 01 00:00:00 EST 1984

DOI:https://doi.org/10.2172/6503679· OSTI ID:6503679

Van Tuyle, G J

A test transient performed at a helical coil sodium-to-water steam generator test facility was simulated using the MINET code. It was determined that correct calculation of the sodium outlet temperature requires representation of heat capacitance of the structure.

• Research Organization: Brookhaven National Lab. (BNL), Upton, NY (United States)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 6503679
• Report Number(s): NUREG/CR-3765; BNL-NUREG-51766; ON: TI84016795
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
STEAM GENERATORS
HEAT TRANSFER
HYDRAULICS
TRANSIENTS
COMPUTER CALCULATIONS
CRITICAL HEAT FLUX
TEMPERATURE GRADIENTS
BOILERS
BREEDER REACTORS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
HEAT FLUX
LIQUID METAL COOLED REACTORS
MECHANICS
REACTORS
VAPOR GENERATORS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding