A method and apparatus for determining the enrichment of uranium dioxide powder is disclosed. A uranium dioxide powder is contained within a closed receptacle having a top, side and bottom wall surfaces. The receptacle is turned upside down so that the uranium dioxide powder is shifted within the receptacle to obtain a more uniform bulk density of the powder contained therein. The natural gamma radiation emission count of the powder is detected while the receptacle is upside down to determine the enrichment thereof.

Systems and methods for a method for determining a critical effective k at an off-rated core state of a nuclear power plant includes determining, for the off-rated core state a control rod density, a percent core power, a gadolinium reactivity worth, a doppler reactivity worth, and a xenon reactivity worth responsive to a control rod pattern, a reactor power plan including the off-rated core state, and a reference effective k, calculating a change in an effective k from the reference effective k at the off-rated core state responsive to two or more parameters selected from the group consisting of the control rod density, the percent core power, the gadolinium reactivity worth, the doppler reactivity worth, and the xenon reactivity worth, and generating the critical effective k for the off-rated core state responsive to the change in the effective k from the reference effective k.

A method of monitoring reactivity changes in a nuclear reaction when the nuclear reaction is subcritical. The method controls the parameter of the nuclear reaction that affects reactivity of the reaction to slightly alter the reactivity while monitoring an output of a source range detector. The Inverse Count Rate Ratio from the output of the detector is determined periodically during a transient portion of the output. A correction factor is applied to the Inverse Count Rate Ratio data and the data is plotted as a function of time. The correction factor linearizes the Inverse Count Rate Ratio data so that the curve can be predictably extrapolated.

The burnout of a fuel element in a reactor is determined by first transferring a fuel element from a reactor to a measuring position and then subjecting the transferred fuel element at the position to a neutron flux. A first detector measures the total .gamma. radiation emitted by the transferred fuel element and thereafter, if the radiation measured by the first detector exceeds a predetermined first limit, the transferred fuel element is returned back to the reactor. If not, a second detector measures a magnitude of high energy .gamma. radiation above 1 MeV emitted by the transferred fuel element and thereafter only if the radiation measured by the second detector exceeds a predetermined second limit, the transferred fuel element is transferred back to the reactor. The element is not returned to the reactor if the radiation measured by the second detector is below the second limit.