Skip to main content
OSTI.GOVU.S. Department of Energy Office of Scientific and Technical Information
U.S. Department of Energy
Office of Scientific and Technical Information
 

Advanced thermohydraulic simulation code for pool-type LMFBRs (SSC-P code)

Technical Report ·
DOI:https://doi.org/10.2172/5094081· OSTI ID:5094081
;
Models for components and processes that are needed for simulation of thermohydraulic transient in a pool-type liquid metal fast breeder reactor (LMFBR) plant are described in this report. A computer code, SSC-P, has been developed as a part of the Super System Code (SSC) development project. A user's manual is being prepared as a separate document. 27 refs., 26 figs., 1 tab.
Research Organization:
Brookhaven National Lab., Upton, NY (USA)
DOE Contract Number:
AC02-76CH00016
OSTI ID:
5094081
Report Number(s):
NUREG/CR-1738; BNL-NUREG-51280; ON: TI86002668
Country of Publication:
United States
Language:
English

Similar Records

Advanced thermohydraulic simulation code for transients in LMFBRs (SSC-L code)
Technical Report · Tue Jan 31 23:00:00 EST 1978 · OSTI ID:6587997
Simulation of operational and safety transients in LMFBR systems. [SSC Code]
Conference · Sat Dec 31 23:00:00 EST 1977 · OSTI ID:5241407
Analysis of loss-of-piping integrity accidents in pool-type LMFBRs using SSC-P
Conference · Wed Dec 31 23:00:00 EST 1980 · OSTI ID:6470891

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BREEDER REACTORS
COMPUTERIZED SIMULATION
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATHEMATICAL MODELS
MECHANICS
PRIMARY COOLANT CIRCUITS
PUMPS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR SAFETY
REACTORS
SAFETY
SIMULATION
TRANSIENTS