Differential Time of Flight Technique for the Detection of Special Nuclear Materials

An adaptation of the differential die away (DDA) technique, which enhances the detection of fissile materials, has been developed and demonstrated in the laboratory. The differential time-of-flight (DTOF) technique applies to situations where special nuclear material (SNM) is located some distance (up to a few meters) away, is accessible from only one side, and is either bare or embedded in an environment that is slightly neutron moderating, and where the more conventional DDA pulsed neutron source technique is less effective. The technique is based on the fission reaction of thermal neutrons with fissile material, if present. The thermal neutrons are furnished by the moderation of neutrons from an electronic neutron generator (ENG). Fast neutrons are generated in relatively narrow pulses of tens to hundreds of microseconds. They are slowed down in a suitable moderator surrounding the source. The time of flight (TOF) of these neutrons, before arrival at the SNM, spreads over orders of magnitude due to the wide spread in their velocities, which lead to a time spread of the neutron-induced fission in the SNM. Neutron signatures resulting from the fissions, e.g., prompt fast neutrons (as well as few delayed neutrons) can then be detected by fast neutron detectors well after the original source neutrons have died away. The fast neutron detectors must be insensitive to the numerous source-related thermal neutrons and are a critical component of the technique, since they can differentiate, by time as well as energy, between the fission signatures and the source-related background. The choice of source moderator is also important to the success of the technique. Two moderators were designed and studied: one made of polyethylene and the other made of beryllium (Be). The latter is superior delivering a higher flux and longer neutron die-away times. The feasibility of the DTOF technique was demonstrated by detecting a sample of 350 g 235U (in the form of 19.9% enriched uranium) at a range of distances and under a variety of conditions employing a commercial (d, T) pulsed neutron generator and the two moderators.