THE PROBLEM OF THE DYNAMICS OF NUCLEAR POWER PLANTS

Journal Article · Thu Aug 01 04:00:00 EDT 1963 · At. Energ. (USSR)

OSTI ID:4693582

Gavrilov, P A; Seliverstov, B N

The results of dynamic tests carried out with a teststand model of the Beloyarsk Atomic Power Station were compared with data obtained by computation techniques of the mathematical model of the same system. Chemically purified water was used in both primary and secondary systems as the heat transfer agent; the secondary loop included a superheater. Both the steam generating and superheating systems were similar to the corresponding portions of the Beloyarsk Station. The heat conductivity equations of the metallic portion of the fuel elements were replaced by thermal balance equations; the continuous pressure gradient in the steam--water and steam portions was replaced by a stepwise changing curve; the axial excessive flow of heat was not taken into account. The amount of heat needed to reach the saturation of the heat capacity of the heat transfer agent was assumed to be independent of the pressure and temperature; the transversal velocity distribution in the heat transfer agent was also taken as remaining constant. The study has shown that the proposed mathematical model is satisfactory for the analysis of dynamic characteristics of test stands and design features of this type of reactors; it may be used for choosing the most suitable control system. The linear model may also be applied to systems with widely differing parameters; the linear and nonlinear models may diverge by as much as 20%. (TTT)

• Research Organization: Originating Research Org. not identified
• NSA Number: NSA-17-042364
• OSTI ID: 4693582
• Journal Information: At. Energ. (USSR), Journal Name: At. Energ. (USSR) Vol. Vol: 15
• Country of Publication: Country unknown/Code not available
• Language: Russian

Related Subjects

CLEANING
CONTROL SYSTEMS
COOLANT LOOPS
EQUATIONS
FLUID FLOW
FUEL ELEMENTS
HEAT TRANSFER
POWER PLANTS
PRESSURE
REACTOR TECHNOLOGY
STEAM
SUPERHEATING
TEMPERATURE
TESTING
THERMAL CONDUCTIVITY
VELOCITY
WATER COOLANT