ANALOG COMPUTER STUDY OF THE TRANSIENT PERFORMANCE OF A DUAL-CYCLE BOILING- WATER-REACTOR NUCLEAR POWER PLANT

Journal Article · Sat Mar 01 04:00:00 EST 1958 · Commun. and Electronics

DOI:https://doi.org/10.1109/TCE.1958.6372752· OSTI ID:4276823

Leiby, D W

A general descrlption ls given of the Dresden nuclear power plant in whlch energy is w'ithdrawn in the form of hlgh-pressure steam obtained by direct boiling in the reactor and from low--pressure steam from a heat exchanger and used to supply the hlgh- and low-pressure stages of a turblne. The steam flow controller is a valve linkage which combines the steam pressures at varlous points in the system with a hydraullc ampllfier. The reacton power level is a functlon of the enthalpy of the inlet water to the core and ls lnfluenced by bubble concentratlons, or volds, in the water. The slmulation of this loop and others ls descrlbed in goneral terms -with several diagrams. The effects oi varlous translents on the steam flow, pressure, turblne load output, and rcactor power level are shown and discussed. (tr-auth)

• Research Organization: Originating Research Org. not identified
• Sponsoring Organization: USDOE
• NSA Number: NSA-13-005143
• OSTI ID: 4276823
• Journal Information: Commun. and Electronics, Journal Name: Commun. and Electronics Vol. Vol: No. 35
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

AMPLIFIERS
ANALOG SYSTEMS
BOILING
BUBBLES
CIRCUITS
COMPUTERS
COOLANT LOOPS
DIAGRAMS
DRESDEN
ENTHALPY
GAS FLOW
HEAT EXCHANGERS
HEAT TRANSFER
HIGH TEMPERATURE
POWER
POWER PLANTS
PRESSURE
REACTIVITY
REACTOR CORE
REACTORS
REMOTE CONTROL
SERVOMECHANISMS
STEAM
TEMPERATURE
THERMODYNAMICS
TRANSFER FUNCTIONS
TRANSIENTS
TURBINES
VALVES
WATER COOLANT
ZONES