Accelerating fissile material detection with a neutron source

1. A system for characterizing a radiation source as fissile material or non-fissile material, comprising:

a DC power supply comprising an AC filter circuit;

a neutron generator coupled to the DC power supply and configured to irradiate the radiation source by inducing radiation in the radiation source;

a detector configured to receive and count neutrons emitted from the radiation source both naturally and from irradiation by the neutron generator; and

an analyzer component coupled to the detector and configured to measure a number of neutrons simultaneously emitted from the radiation source during a number of measurement time periods to derive a multiplet count distribution, compute the mean count rate of the multiplet count distribution, compute the number of pairs of the multiplet count distribution, use the mean count rate to produce a Poisson distribution for the mean count rate, compute the expected number of pairs for the Poisson distribution, subtract the expected number of pairs for the Poisson distribution from the number of pairs in the measurement, and characterize the radiation source as fissile material if the number of pairs in the measurement exceeds the number of pairs for the Poisson distribution.

2. The system of claim 1 wherein the AC filter circuit comprises:

an AC receiving circuit;

a pair of rectifiers converting an input AC signal to respective DC output signals;

a summer circuit receiving the respective DC output signals and configured to add the respective DC output signals together by adding electrical ripple present on a DC output signal from one rectifier of the pair of rectifiers 180 degrees out-of-phase to the electrical ripple present on a DC output signal from the second rectifier of the pair of rectifiers; and

a Cockroft-Walton voltage multiplier circuit coupled to the summer circuit and configured to increase the output of the summed DC output signals to a desired DC voltage level.

3. The system of claim 2 wherein the analyzer component is further configured to:

produce a hypothetical histogram for the Poisson distribution;

produce a count histogram for the count measurement representing a number of times different group sizes occur from the number of measurement time periods; and

overlay the histogram and Poisson count distribution to make a mean count of the hypothetical histogram the same as for the count histogram and to provide a visual indication of the difference in correlation of emitted neutrons from the radiation source, to characterize the neutron source as fissile material or non-fissile material.

4. The system of claim 3 further comprising a component to determine the value of a coefficient, Cn, which represents a number of times that a group of neutrons is observed after repeating a ½ millisecond measurement time period a defined number of times, and wherein the mean count is calculated by the formula:

C

_

=

∑

n

=

0

∞

⁢

⁢

nCn

∑

n

=

0

∞

⁢

⁢

Cn

.

5. The system of claim 4 wherein the shape of the histogram representation of the count measurement is given by the formula:

Cn

⁢

-

⁢

poisson

=

c

_

n

n

!

⁢

e

-

c

_

.

6. The system of claim 1 wherein the neutron generator comprises a pulsed electric source of neutrons irradiating the radiation source using an interrogation beam of neutrons.

7. The system of claim 1 wherein the detector comprises:

a first detector calibrated to a fast time scale on the order of nanoseconds to generate a first set of detected neutrons; and

a second detector calibrated to a slow time scale on the order of milliseconds to generate a second set of detected neutrons.

8. The system of claim 7 wherein the analyzer is configured to analyze the first and second sets of detected neutrons to determine the number of times that a group of n simultaneously emitted neutrons is observed from the radiation source after a defined measurement period is repeated a defined number of times to derive a neutron count measurement based on at least one of the fast time scale and slow time scale to determine whether the material is fissile versus non-fissile.

9. The system of claim 8 wherein the defined measurement time period is ½ millisecond, and wherein a fissile source creates real correlations between the neutrons emitted from the radiation source, and a non-fissile source creates no correlation or only accidental correlations between the neutrons emitted from the radiation source.

10. The system of claim 7 wherein the first detector comprises a scintillator and energy selector system that is configured to detect fast and direct neutrons emitted from the material.

11. The system of claim 10 wherein the second detector comprises at least one of a moderated neutron capture detector or a scintillator-based detector, both configured to detect neutrons emitted from the material in correspondence with the slow time scale.