Doctoral Dissertations
Date of Award
6-1983
Degree Type
Dissertation
Degree Name
Doctor of Philosophy
Major
Nuclear Engineering
Major Professor
Thomas W. Kerlin
Committee Members
P. F. Pasqua, Hall Roland, E. M. Katz
Abstract
Two kinds of balance of plant (BOP) models of a pressurized water reactor (PWR) system are developed in this work - the detailed BOP model and the simple BOP model. The detailed model is developed using basic laws of conservation for each main BOP subsystem. The model may be used to simulate the normal operational performance of a whole POP system. For the sake of economics and because of the limitation of computer capacity, a simple BOP model was developed to combine with the nuclear steam supply system (NSSS) model for a whole plant simulation. The simple BOP model was developed to model the main state variables of the BOP system - the feedwater inlet temperature to the steam generator and the turbine power.
The detailed BOP model consists of the turbine model, the feedwater heater model, the reheater model, the pump model, and the reheater temperature control system model. Both the steam extraction to the feedwater heaters and the internal moisture removal in the turbine stage are considered. The trends of the steady state values are correct. The dynamic response results obtained with the model are reasonable.
The simple BOP model approach starts the modeling work from the overall point of view. Several similar component models are lumped into an equivalent model. The effect of the internal moisture removal in the turbine stage is not considered. The response of the normalized turbine power and the feedwater inlet temperature to the steam generator of the simple model are compared with those of the detailed model. Both the steady state values and the dynamic responses are close to those of the detailed model. The simple BOP model is found adequate to represent the main performance of the BOP system.
The simple balance of plant model was coupled with a NSSS model for a whole plant simulation. The NSSS model consists of the reactor core model, the steam generator model, and the coolant temperature control system.
The PWR plant is treated as an isolated system (no connection to an electric grid). The NSSS system and the BOP system are coupled through the frequency control system, the steam flow control system, and the steam generator feedwater control system.
A closed loop whole plant simulation for an electric load perturbation was performed. The results are plausible. The coupling effect between the NSSS system and the BOP system was analyzed. The feedback of the BOP system has little effect on the steam generator performance, while the performance of the BOP system is strongly affected by the steam flow rate from the NSSS. Due to the delayed characteristics of the low pressure turbine power, the BOP model is required for a whole plant simulation in which the load following mode of operation is of interest. The simple BOP model is good enough for the whole plant simulation in most other cases.
Due to the advantage of simple programming and the suitability for control system analysis, the Continuous System Modeling Program (CSMP) was used as a tool for the simulation. Each component model is written in the form of a modular model. These programs can be applied to a general PWF system with little modification.
Recommended Citation
Wang, Shiren, "Modeling and simulation of pressurized water reactor power plant. " PhD diss., University of Tennessee, 1983.
https://trace.tennessee.edu/utk_graddiss/13160