System and method for performing active scanning of a nuclear fuel rod

1. A method of performing active scanning on a nuclear fuel rod, the method comprising:

generating neutrons with an electrically-driven neutron generator including an ion source, an accelerator, and a target;

moderating the neutrons with a moderator surrounding the neutron generator;

disposing a nuclear fuel rod in a fuel rod channel disposed within the moderator,

wherein the fuel rod channel includes an internal epithermal shell having an inner layer and an outer layer, wherein the inner layer is closer to the fuel rod than the outer layer when the fuel rod is in the fuel rod channel, wherein the inner layer is configured to scatter fast neutrons into an epithermal region, and wherein the outer layer is comprised of burnable poison and configured to absorb thermal neutrons;

subjecting the nuclear fuel rod to a predetermined neutron flux to induce a secondary radiation of prompt and delayed gamma emissions, neutron emissions, or a combination thereof; and

detecting the secondary radiation with a plurality of radiation detectors to determine an amount of fissile material and a spatial distribution of the fissile material along a length of the nuclear fuel rod.

2. The method of claim 1 , wherein the nuclear fuel rod contains a burnable poison.

3. The method of claim 1 , wherein the nuclear fuel rod contains gadolinium or boron.

4. The method claim 1 , wherein the predetermined neutron flux is an epithermal neutron flux, and epithermal neutrons induce the secondary radiation detected by the plurality of radiation detectors.

5. The method of claim 1 , wherein the inner layer is comprised of beryllium.

6. The method of claim 1 , further comprising maintaining a pressure differential within the accelerator.

7. The method of claim 1 , wherein the ion source is a microwave ion source or an electron-cyclotron resonance (ECR) ion source.

8. The method of claim 1 , wherein the target is a solid target comprised of at least one of titanium, copper, zirconium, uranium, palladium or aluminum.

9. The method of claim 1 , wherein the moderator includes a chamber surrounding the target, a neutron moderator surrounding the chamber, and an additional neutron moderator surrounding the neutron moderator.

10. The method of claim 9 , wherein the chamber contains a dielectric solid, liquid or gas.

11. The method of claim 10 , wherein the chamber contains a fluorinert liquid.

12. The method of claim 1 , further comprising disposing a second nuclear fuel rod in a second fuel rod chamber disposed within the moderator.

13. The method of claim 12 , further comprising subjecting the second nuclear fuel rod to a second predetermined neutron flux to induce a secondary radiation of the second nuclear fuel rod.

14. The method of claim 13 , further comprising detecting the secondary radiation of the second fuel rod with at least one of the plurality of radiation detectors to determine an amount of fissile material and a spatial distribution of the fissile material along a length of the second nuclear fuel rod.

15. The method of claim 12 , wherein the second fuel rod channel includes an internal thermal shell having an outer layer comprised of aluminum, and an inner layer comprised of polyethylene.

16. The method of claim 12 , wherein a scanning speed of the first fuel rod channel is slower than a scanning speed of the second fuel rod channel.

17. The method of claim 1 , wherein generating neutrons comprises a total neutron yield of at least 1×10 10 DD n/s.

18. The method of claim 1 , further comprising circulating a fluroinert liquid around the target and the accelerator.