Method of characteristics for solving two-dimensional reactor core flows

Conference · Sun Dec 31 23:00:00 EST 1972

OSTI ID:4394927

Spencer, A C

From national topical meeting on mathematical models and computational technlques for analysis of nuclear systems; Ann Arbor, Michigan, USA (8 Apr 1973). In mathematical models and computational techniques for analysis of nuclear systems. By use of three-dimensional characteristics (two-space dimensions and one-time dimension), a system of compatibility equations equivalent to the mass, momentum and energy conservation equations are numerically integrated along bicharacteristic curves. Included are results which are compared directly with analytical solutions and results representative of possible reactor core transients during accident coriditions. 5 refercnces. (auth)

• Research Organization: Westinghouse Electric Corp., Pittsburgh, PA; American Nuclear Society. Michigan Section
• NSA Number: NSA-29-006865
• OSTI ID: 4394927
• Report Number(s): CONF-730414--P1
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

*PWR TYPE REACTORS-- REACTOR CORES
*REACTOR CORES-- LIQUID FLOW
MATHEMATICAL MODELS
N42300 --Engineering--Heat Transfer & Fluid Flow
N77200* --Reactors--Power Reactors
Non-breeding
Light- water Moderated
Non-boiling Water-cooled
REACTOR ACCIDENTS
THERMODYNAMICS
TWO-DIMENSIONAL CALCULATIONS