Some experimental studies on time-of-flight radiography using a pulsed neutron source

Abstract

Abstract-We are developing a fiber type two-dimentional (2-D) position-sensitive detector having a spatial resolution less than 0.5 mm in order to use it in the time-of-flight (TOF) measurements. The detector performance was examined, and some experiments on the TOF radiography were performed using this detector. The results indicated that the detector could be applied successfully to the TOF measurement and that the TOF radiography was very useful since it gave more informative data than those obtained by the conventional radiography using a broad energy band.Index Terms-Bragg cutoff, cold neutron, fiber type detector, material identification, spatial resolution, time-of-flight.

Research opportunities with compact accelerator-driven neutron sources

“…[91][92][93] Whether it is for application in experiments at the CANS itself or as a part of an instrument at a larger neutron sources, a CANS is definitely a suitable environment for testing new detector concepts. For instance, a number of detector technologies were developed over the years at HUNS, including 2D position-sensitive neutron detectors, [94][95][96][97][98][99] a wavelength-shifting fiber detector, [99] direct-readout pixel-type detectors, [98,100] a boron-type GEM detector, [101] and a neutron image intensifier. [101] A neutron resonance absorption spectroscopy system is also available at HUNS [102] which uses lithium-glass scintillator pixel-type detectors for neutron absorption spectrum recording and BaF2 scintillation detectors for prompt gamma-ray measurements.…”

“…Scintillators are also faster, and count rates of MHz/mm 2 are possible, depending on the photon detection system. Using wavelength-shifting scintillating light fibers, [99] the ultraviolet light from a scintillating screen can be converted to green light in a fiber and transported to multi anode photomultiplier tubes. [105] Spatial resolutions of a few mm have recently been achieved with this approach.…”

“…Tc has such a short half-life, it must be extracted at or near a hospital from a chromatographic column containing 99 Mo (half-life of 67 h) in solution-a 99 Mo/ 99m Tc-generator. Conventional production of 99 Mo is via neutron irradiation of a 235 U target, typically made from fission products containing either low-enriched uranium (LEU) or high-enriched uranium (HEU).…”

“…Conventional production of 99 Mo is via neutron irradiation of a 235 U target, typically made from fission products containing either low-enriched uranium (LEU) or high-enriched uranium (HEU). Therefore, LEU or HEU targets must be shipped to an isotope-producing reactor for irradiation.…”

“…Therefore, LEU or HEU targets must be shipped to an isotope-producing reactor for irradiation. The products are purified in a nearby processing facility, yielding 99 Mo solutions to feed 99 …”