Nuclear power plant modeling and steam generator stability analysis. [TRANSG-P Code]
This thesis describes the development of a computer model simulating the transient behavior of a pressurized water reactor (PWR) nuclear steam supply system (NSSS) and a stability analysis of steam generators in an overall NSSS structure. In the analysis of stream generator stability characteristics, an emphasis was placed on the physical interpretation of density wave oscillation (DWO) phenomena in boiling channels. The PWR NSSS code TRANSG-P is based on the nonlinear steam generator code TRANSG, in which the basic flow channel and heat-exchanger models were previously formulated. In addition to the steam generator, the TRANSG-P code includes models for the pressurizer, the pump, and the turbine. The mathematical model for fluid channels is based upon one-dimensional, nonlinear, single-fluid conservation equations of mass, momentum, and energy. Space and time discretization of these equations is accomplished using an implicit finite-difference formulation. The pressurizer is modeled as a nonequilibrium system at uniform pressure, consisting of vapor and liquid regions. Flashing and condensation are accounted for, and control elements are also modeled. The pump behavior is determined by making use of homologous curves, whereas simple energy conservation and choked flow equations are used to model the turbine. Efforts were made to assess the accuracy of the entire plant model of the TRANSG-P code through simulation of a loss-of-feedwater accident that occurred at a PWR plant. The TRANSG-P results are in reasonable agreement with the plant data, which inherently are subject to considerable uncertainties. In addition, once-through and natural-circulation boiling channel calculations, performed for the investigation of flow stability characteristics, showed good agreement with the test data.
- Research Organization:
- Michigan Univ., Ann Arbor (USA)
- OSTI ID:
- 5336897
- Resource Relation:
- Other Information: Thesis (Ph.D.)
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
COMPUTER CODES
T CODES
PWR TYPE REACTORS
REACTOR COOLING SYSTEMS
FLOW MODELS
STEAM GENERATORS
STABILITY
NUCLEAR POWER PLANTS
SYSTEMS ANALYSIS
BOILERS
COOLING SYSTEMS
ENERGY SYSTEMS
MATHEMATICAL MODELS
NUCLEAR FACILITIES
POWER PLANTS
REACTOR COMPONENTS
REACTORS
THERMAL POWER PLANTS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled