Momentum integral network method for thermal-hydraulic transient analysis. [LMFBR]
Conference
·
OSTI ID:6312353
A new momentum integral network method has been developed, and tested in the MINET computer code. The method was developed in order to facilitate the transient analysis of complex fluid flow and heat transfer networks, such as those found in the balance of plant of power generating facilities. The method employed in the MINET code is a major extension of a momentum integral method reported by Meyer. Meyer integrated the momentum equation over several linked nodes, called a segment, and used a segment average pressure, evaluated from the pressures at both ends. Nodal mass and energy conservation determined nodal flows and enthalpies, accounting for fluid compression and thermal expansion.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6312353
- Report Number(s):
- BNL-NUREG-32444; CONF-830609-1; ON: DE83006493
- Country of Publication:
- United States
- Language:
- English
Similar Records
Transient simulation of a helical-coil sodium/water steam generator
MINET (momentum integral network) code documentation
MINET: transient analysis of fluid-flow and heat-transfer networks
Conference
·
Thu Dec 31 23:00:00 EST 1981
·
OSTI ID:6746172
MINET (momentum integral network) code documentation
Technical Report
·
Thu Nov 30 23:00:00 EST 1989
·
OSTI ID:5193482
MINET: transient analysis of fluid-flow and heat-transfer networks
Conference
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:6364112
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
ACCIDENTS
AFTER-HEAT
BREEDER REACTORS
COMPUTER CALCULATIONS
CONVECTION
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MECHANICS
NATURAL CONVECTION
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AFTER-HEAT
BREEDER REACTORS
COMPUTER CALCULATIONS
CONVECTION
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MECHANICS
NATURAL CONVECTION
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY