POST-NEUTRON MEASUREMENTS AND CALIBRATION PROCEDURES FOR THE AIR FORCE NUCLEAR ENGINEERING TEST REACTOR (thesis)

Technical Report · Sun Mar 01 04:00:00 EST 1959

OSTI ID:4271240

Tardiff, A N

A discussion of the distributed poison method for calibrating control rods and a detailed procedure for calibrating the group rod (all rods acting together) and individual control rods by this method are presented. A method of determining the thermal neutron absorption cross section of the core by use of the inhour equation and the distributed poison method is discussed. Methods of determining the reactivity worth of the core test facilities and components are described. The reactivity worth of the large test cells, beam tubes, bulk shielding facility, fuel element positions, beryllium reflector pieces, and the cadmium curtains are measured by adding or removing poison from the core and by movements of the control rods acting as a group or individually. The other measurements discussed include the shutdown capability of the two least effective control rods, fuel weighting factor for each core position, the temperature coefflcient and the void coefficients using magnesium strips to displace the coolant in the core. A few comments are made about the thermal and fast flux measurements to be accomplished during the calibration phase of the AFNETR. (auth)

• Research Organization: Air Force Inst. of Tech., Wright-Patterson AFB, Ohio
• NSA Number: NSA-13-012266
• OSTI ID: 4271240
• Report Number(s): NP-7368
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

ABSORPTION
AFNETF
BEAMS
BERYLLIUM
CADMIUM
CALIBRATION
CONTROL ELEMENTS
COOLANTS
CROSS SECTIONS
EQUATIONS
FAST NEUTRONS
FUEL ELEMENTS
INHOUR EQUATION
INHOURS
LEVELS
MAGNESIUM
MEASURED VALUES
MOTION
NEUTRON FLUX
NEUTRONS
POISONING
REACTIVITY
REACTOR CORE
REACTORS
REFLECTORS
SHEETS
SHIELDING
SHUTDOWN
STANDARDS
TEMPERATURE
TEMPERATURE COEFFICIENT
THERMAL NEUTRONS
TUBES
VOID COEFFICIENT
ZONES