APPROXIMATE METHOD FOR ANALYZING A NUCLEAR EXCURSION IN A LOW POWER, WATER MODERATED TEST REACTOR

Technical Report · Mon Mar 25 04:00:00 EST 1963

OSTI ID:4702436

Winegardner, W K

An approximate method is presented for analyzing the effects of nuclear excursions in a very low-power, watermoderated test reactor. The analysis was developed to study transients in a reactor consisting of a cylindrical, unpressurized tank containing vertically oriented fuel elements suspended in the moderator. Both metallic and ceramic fuel elements of cylindrical geometry are used. Water in the tank serves as both moderator and coolant. Equations are included in the analysis to estimate the effect of various inherent shutdown mechanisms that exist in reactors of this configuration. Equations are given to determine the reactor power and fuel element core and surface temperature as a function of time. Equations are also included to estimate the reactivity effect of increasing fuel element and moderator temperatures, steam formation at the fuel element surface, and radiolytic decomposition of the moderator. Analog computing techniques are required for rapid analysis because the simulation requires solution of several simultaneous differential equations. (auth)

• Research Organization: General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
• DOE Contract Number: AT(45-1)-1350
• NSA Number: NSA-17-024713
• OSTI ID: 4702436
• Report Number(s): HW-SA-2997
• Country of Publication: United States
• Language: English

Related Subjects

ANALOG SYSTEMS
CERAMICS
COMPUTERS
CONFIGURATION
CYLINDERS
DECOMPOSITION
DIFFERENTIAL EQUATIONS
EQUATIONS
EXCURSIONS
FUEL ELEMENTS
METALS
NUCLEATE BOILING
RADIATION CHEMISTRY
RADIOLYSIS
REACTIVITY
REACTOR TECHNOLOGY
RESEARCH REACTORS
SHUTDOWN
STEAM
SURFACES
TEMPERATURE
TRANSIENTS
VESSELS
WATER COOLANT
WATER MODERATOR