Neutron radiation detector

A neutron flux detector, comprising:

• a Ni-61 source material configured to produce gamma photons during neutron capture;
• and
• a plurality of enhanced gamma sensitivity (EGS) radiation detectors, wherein each radiation detector comprises:
• a Schottky diode;
• and
• an emitter layer comprising a Compton and photoelectron source material, wherein the emitter layer is configured to receive the gamma photons produced by the Ni-61 source material, wherein the emitter layer is spaced apart from the Schottky diode a distance such that a gap is defined between the emitter layer and the Schottky diode, wherein the distance is selected such that only electrons produced by the emitter layer as a result of the emitter layer absorbing the gamma photons will contribute to a measured output signal of the Schottky diode.

A neutron flux detector for use in a fast neutron nuclear reactor, comprising:

• a source material configured to produce gamma photons of a predetermined magnitude during neutron capture when the fast neutron nuclear reactor is in operation;
• and
• an array of enhanced gamma sensitivity (EGS) radiation detectors positioned radially about the source material, wherein each EGS radiation detector comprises:
• a Schottky diode;
• and
• an emitter layer comprising a Compton and photoelectron source material, wherein the emitter layer is configured to receive the gamma photons produced by the source material, wherein the emitter layer is spaced apart from the Schottky diode a distance such that a gap is defined between the emitter layer and the Schottky diode, wherein the distance is selected such that only electrons produced by the emitter layer as a result of the emitter layer absorbing gamma photons of the predetermined magnitude will contribute to a measured output signal of the Schottky diode.