SIMULATION OF THE THERMAL PROCESSES IN THE REACTOR CORE BASED ON AN EXACT SOLUTION OF THE THERMAL DIFFUSION AND HEAT FLOW EQUATIONS

Journal Article · Fri Jun 01 00:00:00 EDT 1962 · Nuclear Sci. and Eng.

OSTI ID:4837712

Ciechanowicz, W

S>The partial differential equations describing thermal processes in the reactor core are solved with respect to the coolant temperature in two cases: that in which the fuel element temperature is averaged over the fuel element cross sectional area; and that in which the temperature distribution in this cross section is taken into account. It is assumed that the fuel element is of the rod type, that there is no conduction in the longitudinal direction, and that the inlet coolant temperature is a constant. The results obtained as solutions of these equations are discussed from the point of view of the application of an analog computer to the exact simulation of thermal processes in the reactor core. (auth)

• Research Organization: Inst. of Nuclear Research, Warsaw
• NSA Number: NSA-16-022314
• OSTI ID: 4837712
• Journal Information: Nuclear Sci. and Eng., Vol. Vol: 13; Other Information: Orig. Receipt Date: 31-DEC-62
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

ENGINEERING AND EQUIPMENT
ANALOG SYSTEMS
COMPUTERS
CONFIGURATION
COOLANTS
DIFFERENTIAL EQUATIONS
DISTRIBUTION
FUEL ELEMENTS
HEAT TRANSFER
REACTOR CORE
RODS
TEMPERATURE
THERMAL DIFFUSION
THERMODYNAMICS
USES