SIMULATION OF A CONTROL SYSTEM FOR A MERCHANT-SHIP PRESSURIZED-WATER REACTOR

Technical Report · Tue Jan 14 04:00:00 EST 1958

DOI:https://doi.org/10.2172/4080875· OSTI ID:4080875

Boyd, R S; Byers, R H; Gordon, B B

A control system for a pressurized-water reactor for use in a nuclear- powered merchant ship was studied by use of analog simulation techniques. The various components of the reactor and primary-coolant loop, including the boiler, were considered. Each simulated component was examined separately and then coupled into the system. With the existence of a large Doppler coefficient of reactivity, the average system temperature could not be maintained within the required limits without external control. Control of the reactor plant through use of a shim-rod mechanism was proposed. Two control schemes were considered. The first system involved control by means of a temperatureerror signal and a power-demand signal. The second consisted of a closed reactor-loop system. A power-error signal was generated by comparing reactor power with a signal proportional to steam flow plus the error in average system temperature and integral of this temperature error. The first system produced acceptable results for only speccific conditions. The closed-loop system satisfled the criteria for plant control; for this control system to be entirely acceptable, the maneuverability requirements must be made compatible with the allowable control- rod reactivity rates. The maximum rates needed for control under a given steam- load-demand change were established. (auth)

• Research Organization: Battelle Memorial Inst., Columbus, Ohio
• NSA Number: NSA-15-012520
• OSTI ID: 4080875
• Report Number(s): AECU-4494 BMI-B&W-639
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

ANALOG SYSTEMS
BOILING
CONTROL
CONTROL SYSTEMS
COOLANT LOOPS
GAS FLOW
IN PILE LOOPS
NEUTRONS
POWER
PRESSURE
PROPULSION
REACTIVITY
REACTOR TECHNOLOGY
REACTORS
SHIPS
SIMULATORS
SPECTRA
STEAM
TEMPERATURE
WATER COOLANT