FAST REACTOR SAFETY. Quarterly Progress Report for the Period Ending March 31, 1961

Technical Report · Sun Apr 30 04:00:00 EDT 1961

OSTI ID:4047087

Agresta, J; Beers, F

Sodium Coolant. Exploratory investigations of transient forced convection heat transfer and a generalized fuel channel study were begun. Reactivity Coefficients. Results are presented for a delayed negative power coefficient of the conduction type acting in conjunction with a prompt (positive or negative) power coefficient. For the negative prompt coefficient, instability never occurs, although finite resonances are possible in the transfer function above some threshold power. For the positive prompt coefficient, instability occurs above a threshold power corresponding to a transfer function resonance of infinite height, and the resorance peak is considerably higher and occurs at lower frequencies than for the negative prompt coefficient. (D. L.C.)

• Research Organization: Nuclear Development Associates, Inc., White Plains, N.Y.
• NSA Number: NSA-15-021726
• OSTI ID: 4047087
• Report Number(s): NDA-2147-6
• Country of Publication: United States
• Language: English

Related Subjects

CONVECTION
FAST NEUTRONS
FREQUENCY
FUEL ELEMENTS
HEAT TRANSFER
LIQUID FLOW
LIQUID METAL COOLANT
POWER
REACTIVITY
REACTOR SAFETY
REACTOR TECHNOLOGY
REACTORS
SODIUM
STABILITY
TRANSFER FUNCTIONS
TRANSIENTS
VARIATIONS