A small break loss-of-coolant accident simulation with MC-PWR
Description
MC-PWR is a microcomputer model for dynamic analysis of pressurized water reactor (PWR) plants. The model simulates all major components of the nuclear steam supply system of the plants with U-tube steam generators, and almost all control systems in the primary and secondary sides of the system. The plant model is based on first-principle formulations using mass, energy and momentum conservation equations for thermal-hydraulics, and point-kinetic formulation for reactor neutronics. Its operation was limited to single-phase flow conditions in the primary side. Currently is is being enhanced to simulate both single-phase liquid and two-phase flow conditions in the primary side to allow simulation of transients such as small break loss-of-coolant accident. In the secondary side the model still assumes subcooled conditions for the feedwater flow, and saturated steam conditions in the steam line. Drift-flux formulations are used to calculate vapor fractions in the different two-phase flow regions in both primary and secondary sides
Additional details
Publishing Information
- Publisher
- University of Tennessee.
- Imprint Place
- Knoxville, TN (USA)
- Imprint Title
- Proceedings of power plant dynamics, control and testing symposium
- Journal Page Range
- p. 33.01-33.03.
Conference
- Title
- 6. power plant dynamics, control and testing symposium.
- Dates
- 14-16 Apr 1986.
- Place
- Knoxville, TN (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18014606
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; EQUATIONS; HYDRAULICS; LOSS OF COOLANT; M CODES; MATHEMATICAL MODELS; MICROPROCESSORS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; R CODES; REACTOR CONTROL SYSTEMS; REACTOR COOLING SYSTEMS; REACTOR KINETICS; SECONDARY COOLANT CIRCUITS; STEADY-STATE CONDITIONS; STEAM; STEAM GENERATORS; SUBCOOLING; THERMODYNAMICS; TRANSIENTS; TWO-PHASE FLOW; VAPORS
- Descriptors DEC
- ACCIDENTS; BOILERS; COMPUTER CODES; CONTROL SYSTEMS; COOLING; COOLING SYSTEMS; ELECTRONIC CIRCUITS; ENRICHED URANIUM REACTORS; FLUID FLOW; FLUIDS; GASES; KINETICS; MICROELECTRONIC CIRCUITS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS